ML20248J351
| ML20248J351 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 10/13/1989 |
| From: | Greer L MASSACHUSETTS, COMMONWEALTH OF, NEW ENGLAND COALITION ON NUCLEAR POLLUTION, SEACOAST ANTI-POLLUTION LEAGUE |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| CON-#489-9308 OL, NUDOCS 8910180133 | |
| Download: ML20248J351 (533) | |
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{{#Wiki_filter:- _ _ - - _ - - kh4b , r CDCKEIED UstiEC UNITED STATES OF AMERICA
~ NUCLEAR REGULATORY COMMISSION 89 OCT 16 P3:32 ATOMIC SAFETY AND LICENSING BOARD' y Before the Administrative Judges:fp ya Ivan W. Smith, Chairman Dr. Richard F. Cole Kenneth A. McCollom
, 1 n ) In the Matter of ) Docket Nos. 50-443-OL
) 50-444-OL PUBLIC SERVICE COMPANY ) (On-site Exercise)
OF NEW HAMPSHIRE, ET AL. )'
)
(Seabrook Station, Units 1 and 2) ) October 13, 1989
)
INTERVENERS' SECOND MOTION TO ADMIT CONTENTIONS ON'THE SEPTEMBER 27, 1989 EMERGENCY PLAN EXERCISE The Massachusetts Attorney General (Mass AG ), Seacoast Anti-Pollution League, (SAPL) , and New England Coalition on Nuclear Pollution (NECNP) , (hereinafter " Interveners",) move this Board to admit additional bases to the contention filed on September 29, 1989 ("JI-Onsite Ex-1") and a new Contention ("JI-Onsite Ex-2") both filed herewith as Attachment A. INTRODUCTION On September 27, 1989 the Applicants conducted an exercise of the Seabrook Station Radiological Emergency Plan (SSRERP). The standard against which that exercise must be evaluated is whether the exercise demonstrated that the SSRERP can be 8910180133 891013 PDR ADOCK 05000443 0 PDR 9
-8 4 implemented.so that there'is reasonable assurance that adequate protective measures can and will be taken in the~ event of a radiological emergency. 10 C.F.R. 9 50.47 (a) (1) . An on-site exercise, such as that conducted on September 27, must be broad enough in scope so that the major portions of the onsite
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emergency response capabilities can be evaluated. 10 C.r.R. , 50.47 (b) (14 ) . The on-site exercise that was conducted was so . 1 abbreviated in-its scope that major portions of the SSRERP were not demonstrated as required by.10 C.F.R. Part 50 Appendix E, sIV.F.1 and 10 C.F.R. 50. 47 (b) (14 ) . JURISDICTION. This Board has jurisdiction over this motion for the reasons previously stated (and by reference incorporated herein) in Intervenor's Motion to Admit Contentions on the September 27, 1989 Emeraency Plan Exercise at pages 3-4. THE STANDARDS FOR THE ADMISSION OF A LATE FILED CONTENTION ARE MET The standards for the admission of a late filed contention are found in 10 CFR S 2.714 (a) (1) (i)-(v) . In ruling on a petition to accept a late-filed contention, a licensing board q must balance the factors set forth in that cited provision. It is well established that the first factor of those standards, good cause for failure to file in a timely manner, is the most crucial factor and weighs most heavily in the balancing test. ALAB-918, NRC _
, Slip Opinion at 21 (1989). CL1-86-8, 23 NRC 241, 244 (1986). To the extent that good cause is shown i
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for a delay in filing contentions, the other factors must be considered much more lightly since they impose a burden on the interveners that would not have existed had the contentions been filed within the time frame permitted under the notice of hearing. When an intervenor establishes that good cause exists for failure to file on time, to give great weight to the other four factors would impermissible burden intervenor's hearing rights. Had the Interveners been able to file the contentions within the initial time period for contentions, they would only have to have met the usual standards for admission of contentions not the additional standards imposed on late filed contentions. TIMELINESS It is clear that good cause exists for the Interveners' failure to file the attached additional bases and contention at the time that contentions were intially required in this proceeding. The Contention arises out of the onsite exercise that took place on September 27, 1989. Since the exercise had not occurred at the time that contentions were originally required to be filed in this proceeding, contentions based upon i that exercise could not be filed at that time. The attached contention is being promptly filed after receipt of the information that gives rise to the contention. The contention is in essence a scope contention challenging the adequacy of the on-site exercise as a meaningful test and an j 1 l l l
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p -l: A' l evaluation of whether the SSRERP can be implemented so that there is reasonable assurance of adequate protection or, conversely,.whether the SSRERP is fundamentally flawed. This scope contention and the additional bases to the earlier contention filed on September 29, 1989~are based upon information derived from the exercise scenario and NRC inspection report on the on-site exercise. These documents were first available to the Interveners on October 10, 1989 and October 12, 1989 respectively.1I Until the Interveners received the information in those documents they were not in a
. position to file the attached contention and amended bases.
While the Massachusetts Attorney General made efforts to observe the exercise, the Applicants refused the Massachusetts Attorney General's request to have observers on-site, at the
'l/ The Massachusetts Attorney General contacted NRC Division of Rules and Records by telephone on September 28, 1989 in an attempt to obtain the scenario document. Previous Freedom of Information Act ("FOIA") requests for the document had been conditionally denied pending the completion of the on-site exercise. Donnie H..Grimsly, Director of the Division of Rules and Records, stated during that September 28, 1989 phone conversation that his office had not yet received a copy of the scenario document. However, he undertook to try to obtain one as quickly as possible and stated that he would forward it as soon as his office obtained it. That phone conversation was followed up by further telephone conversations over the following couple of business days and a follow-up FOIA request in writing on October 4, 1989.
The Inspection Report was first received at the Massachusetts Attorney General's office on October 12, 1989 as an Appendix to Applicant's Response to the Intervenor's Motion of September 28, 1989. It has not to date been received from the NRC by the Mass AG. _4_
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' Emergency Operations Facility, and at the Media Center. That denial relegated the Interveners to being without first hand access to information as to what transpired during the exercise at those sites. Indeed, that denial should effectively estop the Applicant from contending the timely filing of the attached contention since it is being filed within 72 hours of receipt of the scenario document and 24 hours of receipt of the Inspection Report. Prior to receipt of those documents the Interveners did not have and could not have had the information that forms the basis for the attached contention and amended bases to the contention filed on September 29, 1989.
The information upon which those basis are founded is derived directly from those documents. Since those documents were not available at any earlier time, the contention is being filed at the first possible opportunity.2/ Factors 2 and 4. Protection of Interveners and the Petitioner's Interest Represented by Other Parties. For the reasons set forth in the September 29 motion and by reference incorporated herein, these two factors clearly weigh in favor of the admission cf the contentions. Indeed, in the Applicant's October 11 Response to that Motion it is conceded that those factors weigh in favor of the Interveners. Applicants Response at 5. i 2/ As noted in its early motion of September 29, 1989 the Board has still not ruled on Massachusetts Attorney General's renewed motion to establish a schedule. As with the September 29 motion, the motion and contention is being filed now in the event that the renewed motion is denied. j
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E .s-a Revelooment of a Sound Record. By means of the admission of the attached contention and additional bases, the Interveners will contribute to the development of a sound record. The contention and bases sufficiently identify the issues to be decided. The exhibits to the contention make clear that major portions of the SSRERP were not exercised. As set forth in the contention and bases those portions of the SSRERP are required to be exercised as a matter of law. Interveners seeking admission of late filed contentions can establish that their' participation will assist in the development of a sound record by 1) identifying a witness they-plan to present and 2) providing sufficient details of that testimony to permit a licensing board to make a conclusion'as to the worth of that testimony,2/ However, this is not the only way an Intervenor can show that it will contribute to the development of a sound record. There is no need to present a witness when the facts to be presented are not in dispute. Since the contention presents a question of law rather than fact, there is no need for a witness on the issue. Indeed, it would be improper for this Board to accept expert opinion on the question of the proper scope of the relicensing onsite exercise as this is a matter of NRC law. 1/ ALAB-787, 19 NRC 984, 985 (1984); ALAB-747, 18 NRC 1167, 1181 (1983).
6 .- g: The Appeal Board in ALAB-900, 28 NRC 275, 285 expressly recognized the Commission's holding in CLI-86-11, 23 NRC 577, 581'(1986), that litigation on the performance of a relicensing exercise must focus on whether the results of the exercise demonstrate a fundamental flaw. Nevertheless, the Appeal Board rejected LILCO's position that "the design or L scope of the exercise may not be litigated to determine if the exercise was fundamentally flawed". (Emphasis added.) Id. at 285. In rejecting LILCO's argument, the Appeal Board stated at 286-87: Indeed, the necessary, albeit implicit, assumption in the Commission's CLI-86-11 criterion for an admissible exercise contention is that the exercise itself must be comprehensive enough to permit a meaningful test and evaluation of the emergency plan to ascertain if that plan is fundamentally flawed. An intervenor must therefore be allowed to challege the scope of an exercise as too limited. To hold otherwise would allow the unreviewable scope of the exercise to dictate the outcome of the exercise evaluation: i.e., an unduly limited exercise of only a plan's strong points would obviously reveal no fundamental flaws in the plan and, conversely, an unduly limited exercise of solely a plan's weakest areas would doom the outcome of the evaluation to failure. Further, the Commission's regulations themselves provide the predicate for challenging the scope of a pre-license emergency exercise. Section IV.F.1 of Appendix E to 10 C.F.R. Part 50 describes the proper scope of a full participation pre-license exercise and, as such, it imposes regulatory requirements. Assuming that the general subject of such requirements is not otherwise expressly foreclosed from challenge, an intervenor (through the appropriate procedural vehicle) can always raise issues concerning ' compliance with regulatory requirements. Here, given that assessment of an emergency exercise is material to a licensing decision and therefore may be litigated (see UCS, 735 F.2d at 1442, 1445-46), the Governments cannot be denied the opportunity to challenge LILCO's compliance with any of the Commission's regulations concerning emergency exercises, including that addressed to the scope of the exercise. The proposed contentions challenge the Applicants' compliance nith regulatory requirements in the design and scope of the on-site exercise. An assessment of that on-site exercise is material to a licensing decision. ABSENCE OF DELAY The assessment of the fifth factor is one that must, by its nature, be considered to favor the Applicants. obviously, the admission of any new contention will necessarily broaden the , 6 issues to be decided in a proceeding. Therefore, any i meaningful balancing of this factor must consider the dearce to which the issues will be broadened and the deare of delay that will be occasioned by such a broadening. Since the issue in the proposed contentions can be resolved simply by consideration of the relevant law as applied to what are anticipated to be the uncontroverted facts derived from the Exercise Scenario and Inspection Report, it is expected that there can be a determination on the proposed contention even before a decision on the SPMC issues. Since the bases for the contention are founded in law, the Interveners expect to file a motion for summary disposition on the contention within a week. Assuming that the Applicants and Staff respond to that motion within the standard time frame, a decision on the scope contentions could be made well l l l l _ _ _ _ _ _ _ -
d o in advance of November 30, 1989, the date by which a ruling on the SPMC is expected.SI Because the proposed contentions will broaden the issues to be resolved only in a narrow manner and because it is expected that admission of the proposed contention and bases will not occasion delay in the proceeding, the weight to be accorded to the fifth factor is slight. The New Pleadina Standards in 10 C.F.R. 62.714 (b) are not aDolicable. As the statement of considerations issued at the time the new regulations were adopted makes clear, the NRC's new procedural amendments are not applicable to contentions in proceedings that were initiated prior to the effective date of the regulation. 54 Fed Rec. 33179 Since the present proceeding was initiated roughly eight years ago, the proposed contentions fall within the exemption of being contentions in a proceeding initiated prior to the effective date of the new rules. 4/ While the licensing board has previously stated it anticipates that a decision on the SPMC and 1988 exercise will be resolved by November 30, 1989, to the extent that that decision is effected by the question certified by the Appeal Board to the Commission on October 11, 1989, it is possible that that date may not be firmly fixed. 1 I 1 _9_ 1 l 1 1
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07 , - (;gp y4 , The Applicants estoppal argument is' critically flawed: 1)' Estoppel generally runs to issues of fact and not law;
- 2) Applicants in no way. establish that the Commission relied on the Mass AG's earlier erroneous' interpretation of the new procedural rules in denying the application for an exemption; and
- 3) Only the Mass AG, and not the other interveners filing these. contentions,'had earlier made that error and could not be estopped thereby.
CONCLUSION-For all the reasons set forth above, this motion to admit' contentions regarding che scope of the onsite exercise should , 1 be admitted. Respectfully submitted, COMMONWEALTH OF MASSACHUSETTS-JAMES M. SHANNON ATTORNEY GENERAL
/uc 6 Q John Traficonte Chief, Nuclear Safety Unit Leslie Greer Assistant Attorney General Nuclear Safety Unit Department of the Attorney i General i One Ashburton Place l Boston, MA 02108-1698 l (617) 727-2200 DATED: October 13, 1989
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d JI-Onsite Ex-1 Interveners offer the following additional bases.for JI-Onsite Ex-1, previously filed' September 29, 1989, as follows: (1) The scenario failed to meet Exercise Objectives or regulatory requirements since the exercise design did not'
" advance beyond a declaration of site' area emergency and, therefore, did not trigger sufficient'offsite protective action decisionmaking". JI-Onsite Ex-1, p. 3.
Additional Basis The NRC Staff Inspection Report on the Exercise indicates that dose assessment capability was tested, to an' extent, during.the Exercise. NRC Report No. 50-443/89-10 p. 7, attached as Exhibit 1 (" Report").. The Report further indicates, however, that no PARS based upon dose assessment or other factors were actually prepared or implemented during the Exercise. Id. at pp. 7-8. Therefore, there is no assurance that Applicants have the capability to timely identify adequate and relevant information, formulate appropriate PARS, l communicate those PARS offsite, or adjust the PARS based upon changed meteorological or plant conditions, as required by 10 C.F.R. 50.47 (b) (10) ; NUREG-0654 II.J. (3) The scenario failed to meet Exercise objectives or regulatory requirements since the Exercise design did not
" involve the dispatch of any field monitoring teams and monitoring and assessment activities." JI-Onsite Ex-1, p. 3.
I l ATTACHMENT A
l l l l Additional Basis f The Staff Report, Exhibit 1, states that " field monitoring team members arrived at the EOF . .. . (t)he teams were dispatched promptly". Report p. 8. Even assuming deployment into the field of field monitoring teams, the Report indicates only that the sampling procedures were demonstrated. Id. No monitoring procedures or activities were tested even by mini scenario. Therefore, there is no assurance that Applicants are capable of adequately implementing procedures for plume tracking or related monitoring activities as required by 10 C.F.R. 50.47 (b) (9) ; NUREG-0654 II.I. Additional Basis As additional basis for JI-Onsite Ex-1, Interveners rely upon, and incorporate by reference the Staff Report 50-443/89-10, attached as Exhibit 1, and the New Hampshire Seabrook Station 1989 Graded Exercise Scenario, attached as Exhibit 2. JI-On?ite Ex-2 The scope of the September 27, 1989 Exercise (" Exercise") of the Seabrook Station Onsite Emergency Response Plan (" Plan") was so limited that it could not and did not yield valid or meaningful results regarding the capability to implement the Plan, as reqb-led by 10 C.F.R. S 50. 47 (a) (1) and (a) (2) , in that it did not include demonstrations or evaluations of primary procedures, persons, organizations, facilities, or equipment
1 i l 0 l essential to implement the Plan. The Exercise did not test the j adequacy of timing and content of implementing procedures and methods, did not test communications networks or.the public notification system, and did not ensure that emergency organization personnel are competent or familiar with their duties' all in violation of 10 C.F.R.
, 550.47 (b) (14) and 10
- _ C.F.R. Part 50, Appendix E IV.F. Therefore, the willingness, l
, , availability, training, equipment, capability or performance of' the' personnel and entities relied upon to implement the Plan was not adequately tested. The Exercise failed to meet regulatory requirements for an onsite prelicense Exercise, and failed to test as much of the licensee Plan as is reasonably achievable without mandatory public participation in violation of 10 C.F.R. Part 50 Appendix E IV.F.1. The " major observable portions" of the onsite plan which must be demonstrated in the onsite exercise conducted within one year of licensing are those elements in the plan that are required by 10 C.F.R. S50.47(b) (1)-(16) and set out and developed in NUREG 0654, II A-P. ALAB-900. Many of these " major observable portions" of the-Plan were not demonstrated in the Exercise, in violation of 10 C.F.R. Part 50 Appendix E IV.F. BASES A) The scope of the Exercise failed to require or include a demonstration by onsite personnel of an actual shift change or a demonstration of the capability to provide staffing for 1
1 l continuous (24 hour) operations for a protracted period or for second shift staffing in violation of 10 C.F.R. 5 50.47 (b) (1) , NUREG 0654 FEMA Rep. 1, Rev. 1 (NUREG-0654) II.A.4. See New Hampshire Yankee Seabrook Station 1989 Graded Exercise (" Scenario") attached as Exhibit 2. The scenario indicates that a demonstration of these capabilities was not even an Exercise objective. Scenario pp. 2.1-1 to 2.1-3, 3.1-1 to 3.1-12. Similarly, the Staff Report, Exhibit 1, does not indicate these staffing requirements for onsite personnel were exercised, although in the June 1988 Exercise, an exercise objective provided that Applicants " demonstrate the ability to provide continuous 24 hour emergency response capability". Exhibit 3 attached to JI-Onsite Ex-1, p. 2.2-9, filed September 29, 1989. This objective, however, was omitted from the most recent September 27, 1989 Exercise. Therefore, preser<tly there j is no assurance that Applicants have sufficient staff to implement the Plan in accordance with these regulatory requirements. B) The scope of the Exercise failed to require or include a demonstration of the capability for early notification and clear instruction to the populace within the plume exposure EPZ, in violation of 10 C.F.R. 5 50. 47 (b) (5) ; NUREG-0654 II.E. 1 1 The Exercise did not test the public notification system, in j violation of 10 C.F.R. Part 50, Appendix E IV.F, or require Applicants to demonstrate that administrative and physical means have been established for alerting and providing prompt i ________0
.J, i j j 3 1 I instruction to the public within the EPZ, in violation of 10 i i C.F.R. Part 50 Appendix E IV.D.3. The scenario and the Staff i Report indicate a demonstration of these capabilities was not i even an Exercise objective. Scenario pp. 2.1-1 to 2.1-3, 3.1-1 l to 3.1-12. For the Massachusetts EPZ, Applicants failed'to demonstrate mobilization or deployment of their. VANS system, which requires Applicant personnel to drive vehicles to designated locations for siren set-up. This VANS system is= within the exclusive control of Applicants. Yet presently Applicants have not demonstrated the availability of the l vehicles and equipment to implement the system. There has never been an exercise of this public notification system to reasonably assure its adequacy. Applicants could have,.yet failed, to mobilize personnel, direct these personnel to designated locations, and set up the sirens in preparation for activation. Therefore, there is no assurance that Applicants' VANS system, to be staffed and operated by Applicant personnel, ( vill properly and adequately notify the public in an actual emergency. C) As additional basis for JI-Onsite Ex-2, Interveners rely upon, and incorporate by reference the Staff Report 50-443/89-10, attached as Exhibit 1, and the New Hampshire Seabrook Station 1989 Graded Exercise Scenario, attached as Exhibit 2. ' i ______a
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U. S. NUCLEAR REGULATOPY COMMISSION REGION I Report No. 50-443/89-10 Docket No. 50-443 License No. CPPR-135 Priority -- Category [ Licensee: Public Service Co. of New Hamoshire P.O. Box 330 Manchester. New Hampshire 03105 Facility Name: Seabrook Station Inspection At: Seabrook. New Hamoshire \ Inspection Conducted: September 26-28. 1989 Inspectors: kLa k E.
;. Fox, Jr., Sr. Emergency Preparedness lob f 9T Specialist, EPS, FRS&SB, DRSS /date C. Amato, EPS, FRS&SB, DRSS A. Cerne, SRI, Seabrook Nuclear Power Station R. Serbu, PEPB, NRR W. Laza us, Chief, EPS, FRS&SB, DRSS we Approved by:_W. V.Jazpfu), Chief, Emergency Sec;rion, FR$&SB, DRSS
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date Preparedness Insoection Summary: Insoection on September 26-28. 1989 1Recort No. 50-443/89-10) Areas Insoected: observation of the licensee's partial-participation annual emerg preparedness exercise conducted on September 27, 1989. performed by a team of five NRC Region I and headquarters personnel.The inspection wa Results: No violations, deviations or unresolved items were identified. The licensee's response actions for this exercise demonstrated the ability to implement the emergency plan in a manner which would provide adequate protective measures for the health and safety of the public.
'l DETAILS 21.0 Persons Contacted
, The.following . licensee representatives attended the exit meeting held on September 28,.1989.
q S.lBuchwald, Quality Assurance Supervisor R. Boyd, Jr., Performance Services Manager ,
'E. Brown, President A. Callendrello, Manager, Emergency Planning Licensing P.' Casey, Senior Emergency Planner E. Desmarais, Independent Review Team Manager B., Drawbridge, Executive Director Nuclear Production J. Ellis, Manager, Response and Implementation T.'Feigenbaum, Chief Operating Officer and Sr Vice President T.' Grew,' Manager, Specialty Training J. Grillo, Operations Manager T. Harpster, Director, Licensing Services J. MacDonald, Radiological Technical Specialist J. Martin, Manager, Community Relations D. McLain,? Production Services Manager D. Moody, Station Manager P. Richardson, Manager, Training
- N. Pillsbury, Director,: Quality Progrcus P. Stroup, Director, Emergency Implementation and Response W. Sturgeon, Nuclear Services Manager R. Sweeny,- Bethesda Licensing Office Manager D. Tai 11eart, Emergency Preparedness Manager J. Tefft, Lead Engineer
- R..Winn, Director, Corporate Communications During the conduct of the inspection, other licensee emergency response personnel _were interviewed and observed.
2.0 Emeroency Exercise The Seabrook Station _ partial-participation exercise of the licensee's on-site Emergency Plan was conducted on September 27, 1989, from 8:00 a.m. until 3:30 i." p.m.- FEMA did not observe. There was limited off-site participation of State of New Hampshire Incident Field Office (IFO) and the licensee's Off-site Response Organization (ORO) to test the interface with the licensee's on-site emergency response' personnel. 1 2.1 Pre-exercise Activities The exercise objectives submitted to the NRC Region I on June 30, 1989 were reviewed and determined to adequately test the licensee's Emergency Plan. On July 27,-1989, the licensee submitted the complete scenario package for NRC review and evaluation. Region I representatives had telephone conversations l with the licensee's emergency preparedness staff to discuss the scope and content of the scenario. As a result, minor revisions were made to the scenario and supporting data provided by the licensee. As this was a partial-participation exercise, it was not necessary to demonstrate off-site I'
I i 3 protective actions. It was determined that the scenario would support an adequate partial-participation exercise of the licensee's Emergency Plan and Implementing Procedures. The scenario involved a loss-of-coolant accident j which would result in declaration of a Site Area Emergency and would test the i licensee's on-site emergency response facilities including the functions of ; dose assessment, protective action decision-making, and the interface with the ; State of New Hampshire ~ officials and the OR0, which compensates for the lack j of participation by the Commonwealth of Massachusetts. Although a major - 1 release of radioactivity was not included in the scenario, the existence of the potential for such a release would force the demonstration of the major ' areas of the licensee's emergency response organization. NRC observers attended a licensee briefing on September 27, 1989 and participated in the , discussion of emergency response actions expected during the scenario. It was ! agreed that controllers would intercede in exercise activities to prevent scenario deviations or disruption of normal plant operations. The exercise scenario included the following events: Loss of both emergency diesel generators requiring declaration of an UNUSUAL EVENT;
-- A leak in the reactor coolant system of greater than 50 gallons per minute from the Resistance Temperature Detector (RTD) manifold return line isolation valve requiring declaration of an ALERT; A small break loss-of coolant accident (LOCA) from the RTD manifold requiring declaration of a SITE AREA EMERGENCY.
The above events caused the activation of the licensee's on-site emergency response facilities and demonstration of the interface with the OR0 and the State of New Hampshire. 2.2 Activities Observed During the conduct of the licensee's exercise, NRC team members made detailed observations of the activation and augmentation of the emergency response organization, activation of emergency response facilities, and actions of emergency response personnel during the operation of the emergency response facilities. The following activities were observed:
- 1. Detection, classification, and assessment of scenario events;
- 2. Direction and coordination of the emergency response;
- 3. Notification of licensee personnel and off-site agencies;
- 4. Communications /information flow, and record keeping;
- 5. Assessment and projection of radiological dose and consideration of protective actions;
- 6. Provisions for in-plant radiation protection;
- 7. Performance of off-site and in-plant radiological surveys;
- 8. Maintenance of site security and access control;
- 9. Performancti of technical support, repair and corrective actions;
- 10. Assembly and accountability of personnel; and
- 11. Provisions for communicating information to the public.
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- 3.0 Classification of Exercise Findinas Emergency Preparedness exercise findings are classified as follows:
Exercise Strenaths Exercise-strengths are. areas of the licensee's response that provide ' strong positive indication of the ability to cope with abnormal plant conditions and implement the emergency plan and procedures. Exercise Weaknesses Exercise weaknesses are' areas of the licensee's response in which the performance was such that it could have precluded effective implementation of the emergency plan in the event of an actual emergency in the area being otserved. Existence of an exercise weakness does not of itself-indicate that the overall response was inadequate to protect the health and. safety of the public. Areas for Improvement An area for improvement is an area which did not have a significant negative impact on the :.bility to implement the emergency plan and response was adequate; however it should be evaluated by the licensee to determine if corrective action could improve performance. 4.0 Exercise Observations The inspectors observed licensee response actions in the emergency response facilities as follows: Control Room (The licensee' simulator was used) Several exercise strengths were identified.
- 1. The shift crew demonstrated alertness and fast response to alarms and indications. For example, the increased leakage from the reactor coolant system was quickly identified and quantified based on decreasing pressurizer level before any alams were received which would have brought it to the operators' attention.
- 2. The Shift Supervisor (SS) completed correct preliminary classification of the UNUSUAL EVENT in 2 minutes and announced it as soon as the loss of the second diesel generator was confirmed by the auxiliary operator (total elapsed time of 4 minutes).
- 3. Notifications of the UNUSUAL EVENT were made to the states within 3 minutes and the NRC within 9 minutes of the classification of the event. Since the exercise involved the use of the simulator control room rather than the actual control room, these times are based on when the operators simulated the use of the " orange"
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3 5 phone (used for notification of New Hampshire and Massachusetts) and the NRC Emergency Notification System phone in the simulator a control room. These emergency phones are. not capable of being used from the simulator. In;an actual event, the calls are made-from phones which are operable in the plant control _ room. ,
- 4. The Shift Supervisor / Shift Techncial_ Advisor (SS/STA) conducted frequent, independent critical safety function checks of the - -
plant. is '5. There was excellent communication among the shift personnel.- o
- 6. Correct recognition of and adherence to Technical Specification' Action Statements were demonstrated.
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- 7. Routine operations and emergency procedure compliance were professional and precise.
- 8. Good communication was maintained with emergency response-personnel outside the control room. An additional licensed.
operator reported to the control room after'the declaration of the ALERT to set up and maintain direct on-line communications with the Technical Support Center (TSC) and Operations. Support Center (OSC).-- This aided in establishing priorities for direction of repair and troubleshooting activities outside the control room. One area for improvement was brought to the licensee's attention: The transfer of authority from the Short Term Emergency Director (STED) (Shift Supervisor in the Control Room) to the Site Emergency Director (SED) in the Technical Support Center was not announced on the plant paging system. Although the STED and SED were both clearly aware that the transfer had occurred, announcement of that fact may be beneficial to other emergency response personnel. Technical Suncort Center Several exercise strengths were identified.,
- 1. Appropriate engineering solutions were pursued to correct or.
mitigate casualties to equipment, including Use of both a fire truck and compressed gas cylinders on-site to recharge the emergency diesel generator air bank; Use of the site-specific Probabilistic Risk Assessment to identify probable locations of the reactor coolant system leakage and the subsequent small-break LOCA. i
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' 2 '. Additional support was sought from and use was made of Yankee Atomic Service Department to. identify the location of the reactor coolant system leakage.
- 3. Communications _were. effective and continuous.
- 4. ~ Effective use was made of status boards which were updated every fifteen minutes. Data relating to Regulatory Guide 1.97 accident variables were trended, including extrapolation of Refueling Water Storage. Tank level and interpretation of the trend. Plots were cross correlated. D
- 5. Discussions were held.regarding the potential need for prctective actions and at what point.they would become necessary if conditions worsened..
- 6. The TSC effectively coordinated OSC personnel to determine plant conditions and'effect repairs.
Two areas-for improvement were brought to the licensee's attention: Within the Technical Support Center, two instances of telephone line noise occurred, causing some minor communications problems during the exercise; Boron concentration curves should be reviewed to verify that they cover all reasonably expected conditions. Operations Suncort Center Several exercise strengths were identified.
- 1. Excellent command and control was demonstrated.
- 2. Dispatch of repair _ teams was timely and proper. Approximately nine (9) teams were used in accordance with repair efforts determined by the TSC.
- 3. Information from the repair teams, including results of both containment air and reactor coolant samples obtained from the Post Accident Sampling System (PASS) were rapidly provided to decision makers at the TSC end the Emergency Operations Facility.
- 4. Excellent in-plant radiation protection precautions were instituted and maintained throughout the exercise.
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C , i o 7: q Emeroency Ooerations Facility (EOF) 'l , 1 Several exercise strengths were identified.
- 1. The EOF was activated promptly and was operated effectively. !
. Actions by response personnel were timely and in accordance with l procedures. 1 lj
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- 2. Coordination and communication with other emergency ~ response facilities including the TSC, ORO, and the New Hampshire IFO were ;
frequent and effective as were communications between the various F divisions of the EOF emergency response staff. i
- 3. Technical assessment was clearly.in evidence throughout the .;
exercise. Any suspected inconsistencies between various pieces of ! information were questioned and resolved. q
- 4. Emergency communications (news releases) were effectively prepared, reviewed and approved.
- 5. Radiation Monitoring Teams were effectively staged, dispatched and I' directed.
- 6. Dose assessment capability was promptly established using the backup Hewlett-Packard HP41-CV calculator after the scenario indicated failure of the METPAC system primary, backup, and Yankee Atomic computer systems to force use of the HP41-CV' system.
Several proposals were made which would have quickly re' ared the METPAC computers to operation, however in order t- test the backup, they were prevented from being , implemented by the exercise controllers. Several "what if" projections were made for potential events with radioactive material releases including steam generator tube rupture, containment venting, and containment failure. J Field samples were received and promptly counted in accordance with procedures. ) 1 Meteorology was kept current and forecast conditions { carefully evaluated. The effect of any potential wind shift J on protective action considerations was considered.
- 7. Effective security was maintained at the EOF. Persennel accountability results were provided to both the EOF and TSC Managers in a timely manner.
- 8. Possible protective actions were discussed with the ORO and New Hampshire IFO. These discussions were frequent and effective and included the determination of potentially affected areas and consideration of whether school children should be dismissed at i
l
l it. 8 l the normal end of the school day or held at school where they could be more easily evacuated if conditions worsened. Conditions I considered included plant evolutions such as the switchover from the injection to the recirculation mode and the stability of projected weather conditions. Field Monitorina Teams Several exercise strengths were identified.
, 1. Field monitoring team members arrived at the EOF promptly and effectively prepared for riispatch.
The teams performed thorough monitoring kit inventory, instrument checks including source checks, portable air sampler checks, radio checks, and vehicle checks in accordance with their procedures. Personnel were very knowledgeable of the proceduces and demonstrated proficiency and a good understanding of their responsibilities. Good radiological practices were followed in the set-up of the vehicle bay used for the dispatch of the teams and ' receipt of samples. Teams were thoroughly briefed on plant conditions and expected radiological conditions prior to dispatch. Team members received appropriate dosimetry prior to dispatch.
- 2. The teams were dispatched promptly (within 50 minutes of arrival at the EOF).
- 3. Communications between the E0F and the field teams was excellent.
- 4. Sample counting equipment was set-up promptly.
- 5. Sample control and analysis including surveys and the use of anti- ;
contamination clothing were effectively demonstrated.
- 6. A personnel monitoring and decontamination station was established in the vehicle bay, using effective procedures f>r control of access and egress, installation of floor coverings, use of survey equipment, and manning the control point.
l l 3 l
c-c= , . l' 9 Media Center / Joint Teleohone Information Center Several exercise strengths were identified.
- 1. Activation, staffing, and command and control were effectively and efficiently accomplished.
- 2. Information was obtained through authorized officials, and appropriately coordinated and reviewed prior to release to the public.
- 3. Information provided to the public was clear, concise and accurate.
- 4. Rumor control was effective. Media Center rumor control personnel promptly sought verification of rumors and provided the correct information in all cases.
- 5. Responses to questions posed by exercise controllers simulating press personnel to media briefers were detailed and understandable.
Overall Conclusions The NRC team noted that the licensee's activation and augmentation of the emergency organization, activation of the emergency response facilities, and use of the facilities were consistent with their emergency response plan and implementing procedures. No exercise weaknesses were identified. The licensee demonstrated the ability to implement the emergency plan in a manner which would have provided adequate protection for the health and safety of the public.. 5.0- Licensee Critiaue and Exit Interview The licensee conducted an adequate self-critique of the exercise. There were no exercise weaknesses identified. Following the licensee's self-critique, the NRC team met with the licensee representatives listed in Section 1 of this i report to present exercise observations as detailed in this report. i At no time during this inspection did the inspectors provide any written information to the licensee. 1 i
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SEPTEMBER 27,'1989 TABLE OF CONTENTS s' ' l' ' -. h
;1.0 Planning Elements 2.0 Exercise Objectives 3.0 Exercise Guidelines' o
L 4.0 ' Exercise Contr01 : 5.0 ' Narrative Summary 6.0 Sequence of Events
. 7.0 ' Messages
' 8.0 Mini-Scenarios 9.0 Plant Parameters 10.0 Radiological Data 11.0 Reference Matertal
'12.0 Evaluation Material EXHIBIT 2-
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;NEW HAMPSHIRE' YANKEE:
'SEABROOK STATION
~1989-GRADED EXERCISE.
t. l l Date G. R. Gram Executive Director Emergency Preparedness and Community Relations Date D. E. Moody Station Manager 1.1-1
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,i TABLE OF CONTENTS; 1.0 Planning Elements 2.0 Exercise Objectives 3.0 L Exercise Guidelines , l 4.0 Exercise Control 5.01 Narrative Summary 6,0 ' Sequence of Events 7.0 Messages 8.0 ' - Mini-Scenarios o
9.0 Plant Parameters'- 10.0 Radiological Data 11.0 Reference Material 12.0 Evaluation Material 1 EXHIBIT 2 =L_________---_-.-_-- --
la NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 1.0 PL ANNING ELEMENTS 4 9 l l l l 1 l l' 1 l' l
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1 i r l' l NEW HAMPSHIRE YANKEE I1 SEABROOK' STATION
-1989 GRADED EXERCISE Date G..R. Gram Executive Director Emergency Preparedness and Community Relations i
Date D. E. Moody Station Manager 1.1-1
f.i , NEW HAMPSHIRE YANKEE SEABROOK STATION i; . I;- 1989 GRADED EXERCISE PIANNING ELEMENTS Exercise Date Wednesday, September'27, 1989 Commencement Time: September 27 - 0745 L Exoected Durations' September 27 - Approximately 8 hours , Controllers: Controllers are listed in Section 4.0 of this exercise manual. Players: September 27 . Red Team Emergency Response Organization Locations: All NHY Emergency Response Facilities as delineated in Section 3.0 Exercise Guidelines. Obiectives: See Section 2.0 Critique Lccation and Time : Following exercise in each emergency response facility. l 1.1-2
NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 2.0 EXERCISE OBJECTIVES i 1 i i
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'ONSITE GRADED EXERCISE OBJECTIVES
- 1. Demonstrate the ability of the Emergency Response Organization to activate the Radiological Emergency Plan and implement appropriate associated procedures.
- 2. Demonstrate the ability to identify initiating conditions, assess Emergency Action Level (EAL) parameters and correctly classify the emergency.
- 3. Demonstrate the ability to analyze station conditions, parameter trends and develop potential solutions for placing the unit in a safe, stable condition.
- 4. Demonstrate the ability to assemble and dispatch emergency -
teams to perform response activities.
- 5. Demonstrate the ability to notify and mobilize the Emergen,cy Response Organization.
- 6. Demonstrate the ability to notify the States and the NRC within the required time limits.
- 7. Demonstrate the ability to notify onsite personnel of emergency conditions.
- 8. Demonstrate the ability to transfer appropriate notification i
responsibilities from the Control Room to the TSC and EOF.
- 9. Demonstrate the ability to provide current information to offsite emergency response personnel.
- 10. Demonstrate the ability to perform assessments of onsite and offsite conditions to support the formulation of Protective Action Recommendations (PARS).
- 11. Demonstrate the ability to formulate and communicate PARS to appropriate offsite officials.
- 12. Demonstrate the ability to formulate protective actions for emergency response personnel including area access control, exposure control, use of protective devices, and if appropriate, the decision process for administration of potassium iodide (KI).
- 13. Demonstrate, if appropriate, the decision-making aspects for authorizing emergency workers to receive doses in excess of 10CFR20 limits.
2.1-1 j I I - _ - _ _ _ . s
ONSITE GRADED EXERCISE OBJECTIVES (continued)
- 14. Demonstrate the ability to perform offsite dose assessment.
- 15. Demonstrate the ability to mobilize and direct field monitoring teams.
- 16. Demonstrate the ability of emergency response personnel to conduct radiological monitoring activities including dose rates, sample collection and sample analysis.
- 17. Demonstrate the ability to activate emergency response facilities in a timely manner.
18. Demonstrate that facility layout and equipment adequately support emergency response activities in each facility.
- 19. Demonstrate the operability and effective use of '
communications equipment.
- 20. Demonstrate the ability of the Site Emergency Director (SED) to maintain control of the emergency response effort onsite and the Response Manager to maintain overall control of the emergency response effort once the EOF is activated.
- 21. Demonstrate the ability to gather, assecs, coordinate and disseminate information regarding station conditions and emergency response activities.
- 22. Demonstrate the ability to transfer appropriate command functions from the Control Room to the TSC and EOF.
- 23. Demonstrate the ability to coordinate preparation, review and release of public information.
- 24. Demonstrate the ability to provide offsite emergency response organizations with accurate post-accident assessments.
- 25. Demonstrate the ability to communicate with all appropriate locations, organizations, and field personnel, with special emphasis on communications between field monitoring and sampling teams and their command center.
- 26. Demonstrate the ability to interface, communicate and coordinate emergency response actions with offsite emergency response organizations.
2.1-2
-l ONSITE GRADED EXERCISE OBJECTIVES (continued)
- 27. Demonstrate the ability to evaluate sample analysis data-and/or field measurements and provide appropriate protective action recommendations and interface with offsite response organizations.
- 28. Demonstrate the. ability to provide timely and accurate information to the media and general public.
- 29. Demonstrate the ability to establish and operate rumor control functions.
- 30. Demonstrate the ability of the Emergency Response Organization to conduct a self-critique and identify improvement areas.
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YM EXERCISE ' GUIDELINES / EXTENT OF ~ PIAY p< LNOTE: NumberingJsequence is identical' to the sequence in. Section 2. 1 ".- The Seabrook Station Emergency. Response OrganizationJwill demonstrate this objective. Initial activation will start gr in the Control Room.- The Control Room'will'be simulated by-th_e: Training Center. Simulator.. A simulator. controller will be stationed'with the' Exercise - Shift Superintendent and will be on a telephone link with 1 the actual. Shift Superintendent Controller in the Station. Control Room. Actions initiated by the Exercise' Shift Superintendent in the Simulator will be relayed to the Shift-Superintendent Controller. The Shift Superintendent L Controller will duplicate the actions associated with, notifications, forms' completion, and immediate' interface with TSC responders'in the Control Room based on decisions
-made by the-Exercise Shift Superintendent. All notifications will be conducted'from the Station Control-
~ Room.
All.Seabrook-Station emergency response facilities'will be' manned-in a1 timely fashion and perform prescribed functions in accordance with station procedures as appropriate to the developmentLof.the exercise scenario. TheLfollowing Seabrook Station Radiological Emergency Plan organizations will participate in this exercise: (1) Control Room / Simulator Control Room-(2) -Technical Support Center'(TSC) (3)- Operational Support Center.(OSC)-
; (4) Emergency Operations Facility (EOF)
(5) Media Center:
,, -(6) Joint Telephone Information Center (JTIC)
- 2. The Centrol Room and the TSC will demonstrate this objective. ~ The accident condition does not have to escalate through all classes.
- 3. The Control Room, TSC and EOF will demonstrate this objective. A data link between the Simulator Control Room, TSC and EOF will be maintained for the purpose of providing Main Plant Computer System (MPCS) data. MPCS logger trend sheets detailing dose assessment and operational trend data 3.1-1
EXERCISE GUIDELINES / EXTENT OF PIAY (continued) I will be issued every 15 minutes provided the logger trend feature is accessed. Simulator controllers will change the { operational trend data as player action changes the accident { sequence; however, no operational action will be allowed j which changes the main timeline. l J t The use of the Safety Parameter Display System (SPDS) will be simulated during the exercise. 4. The TSC, OSC and EOF will demonstrate this objective. The OSC will dispatch teams necessary to respond to events within the Seabrook Station protected area. Use of protective clothing and respiratory protection shall be demonstrated in accordance with Objective 12. A maximum of three (3) Seabrook Station Offsite Monitoring Teams will be assembled. One team will be dispatched from the EOF for the purpose of testing response time, ' communications, and monitoring and sampling procedures. In ! the event that the team is not directed to take samples due to scenario response, the team controller will issue direction to conduct an out-of-sequence demonstration of sampling techniques. The use of protective clothing and respiratory protection equipment, and the administration of KI by offsite emergency response personnel shall be simulated. On-shift Auxiliary Operators who are normally dispatched by the Control Room will be simulated by two (2) simulator instructors using the methodology employed during licensed operator training sessions. , i
- 5. The Control Room and Security will demonstrate this l objective by notifying the primary and backup responders of l the Seabrook Station Emergency Response Organization.
Backup 'aemergency response organization members will be
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l These personnel will be held until the EOF directs the Assembly Area Coordinator to release the backup staff. Backup emergency response organization members will be allowed to return to work. The interface with Yankee Atomic Electric Company (YAEC) Engineering Support Center (ESC) l will be provided. Notification and mobilization of this organization will be initiated by security activating the YAEC pager system. A partial Engineering Support Center staff will be mobilized for this exercise. 3.1-2 i
EXERCISE GUIDELINES / EXTENT OF PLAY (continued) Three in~themembers area. offYAEC Site Response Team will be prestaged They will be notified to report to the TSC and EOF at a predesignated time warranted by scenario action.
- 6. The Concrol Room, TSC and the EOF will demonstrate this objective.
Offsite Response Organization (ORO) will be simulated by selected Controllers in order to accept emergency declaration, PARS, and VANS notification communication interfaces with ERO. The State of New Hampshire Response Organization will be simulated by selected Controllers in order to accept emergency with ERO. and PAR notification communication interfaces declaration l a. Initial State Notification t Information for these notifications will be identified and recorded by the Exercise Shift Superintendent in the Simulator Control Room. Upon receipt of a completed ! Form ER-2.0B, State Notification Fact Sheet from the Exercise Shift Superintendent, the simulator controller will contact the Duty Shift Superintendent in the Station Control Room and relay specific form content. The 15-minute clock for required State notifications l will begin when the Shift Superintendent Controller completes Form ER-2.0B. Upon receipt of this information the Shift Superintendent Controller through the Communicator will: l establish actual Nuclear Alert System (NAS) telephone contacts (State of NH and NHY ORO) establish contact with a controller located in phone cell simulating the Commonwealth of Massachusetts , i transmit information contained on Form ER-2.0B to State discatcher and NKY ORO EOC Contac* transmit information contained on Form ER-2.0B to the controller simulating the Commonwealth of Massachusetts State Dispatcher ensure parties acknowledge receipt of this " Drill" message l 3.1-3 I : L L_________------- i
EXERCISE GUIDELINES / EXTENT OF PLAY (continued) f
-i Upon verification by the State contacts of the initial notification, the Shift Superintendent _ i Controller will fax the completed Form 2.0B back to j the Simulator for use by the Exercise Shift -]
Superintendent. ' Responsibility for making _ State notifications will remain with the Site' Emergency Director or the Short Term Emergency Director until the EOF is activated. The Control Room State NAS group call nwnber XXX will be failed for the exercise. The State of New Hampshire NAS contact number for the exercise is XXX. The'ORO EOC Contact NAS contact number for the exercise is XXX. The Commonwealth of Massachusetts contact will be to a designated phone cell number.
- b. Follow-up Notifications The Exercise Shift Superintendent will complete Form j 2.0C, Follow-up Information Form. Upon receipt of the '
completed form, a simulator controller will fax the-information to the Shift Superintendent Controller or Site Emergency Director, whoever is available at the~ time of completion.
~l The' Exercise Shift Superintendent or Site' Emergency Director or Control Room Communicator will respond to controllers simulating New Hampshire State Health Department, ORO EOC Contact, and Massachusetts DPHS call-backs. All call-backs will be' forwarded to the Exercise Shift Superintendent until such time that the
' State turnover crocess has haan --mn'o+=d "' " " ' *tt?
, smergency Director.
Follow up calls by controllers representing New Hampshire Health Department, ORO EOC Contact, and Massachusetts DPHS representative will be placed to commercial line (603) XXX-XXXX (this line is located in , the Control Room and the TSC). 3.1-4
l' +
,n EXERCISE. GUIDELINES / EXTENT OF PLAY 7:
(continued)
, *2 .
y Once the. EOF is operational,-the Corporate Support-Manager will continue theLState notification process fors escalations in emergency classification levels and/or protective action recommendations in.the following manner: , I The EOF / State NAS group call-number.XXX will be' ;
. failed-for the exercise.
l - The' State of New. Hampshire EOC'NAS contact number for the exercise is XXX. j l- - The-ORO EOC NAS contact number.for the exercise-is XXX. The Commonwealth of Massachusetts civil Defense Agency contact and DPHS contact will be through a phone cell communication. c.. NRC Notifications The NRC will be contacted for the initial classification-and again once the exercise has terminated.. The Shift-Superintendent Controller will make'this notification using Form'ER-2.OD, NRC Event Notification Worksheet. < This information will be transferred-from the Simulator l (by fax) using the methodology described for State notifications. This responsibility will be transferred to the Emergency Operations Manager (EOM):upon TSC activation. The EOM will' process Form ER-2.0D for major l events. A Control Cell Controller will contact the EOM every half hour' requesting a status update simulating 4 the continuous phone contact. The Health Physics Network (HPN) phone will be simulated
] from the control cell unless required to be maintained throuch rene.= - A*'
-'S "og j;_-1,,- -',- i,,1,i;i notifications. A control cell number will be issued to appropriate players.
- 7. The Control Room will demonstrate this objective within the i Protected Area through the use of emergency alarms and the j site Gaitronics (plant paging) System. . Remaining station 4 personnel will be notified by either mechanical or verbal )
notification methods implemented by security. All I announcements must be preceded with "This is a drill." 3.1-5
\
I 1 I EXERCISE GUIDELINES /EITENT OF PLAY (continued) 8. The TSC will demonstrate a transfer of State and notification responsibilities associated with the Nuclear Alert System (NAS), and Public Alert Notification System j (PANS) to the EOF who, in turn, will transfer responsibility for PANS to the ORO controller. ' l 1 9. This objective will be demonstrated by the Control Room, TSC and EOF. The Control Room and-TSC will provide initial State call back information and the EOF will provide 'j subsequent State and field team information to controllers representing the normal State interfaces. All communication to non-participating areas / agencies will be directed to the l control cell. Offsite augmentation agencies (simulated by Controllers) will be contacted as required by appropriate procedures. Each call MUST be preceded and followed with "This is a drill."
- 10. This objective will be demonstrated by the Control Room, TSC and the EOF. The Control Room will issue the predesignated PAR based on classification level. The TSC and the Control Room will monitor plant conditions to support the formulation of PARS and will transfer the responsibility to the EOF upon activation.
Radiological data generated by the simulator during the development of the scenario, and during the exercise run, will not be used. This data will be superceded by developed data, the magnitude of which, will effectively drive the l exercise. Controllers will issue Radiological Data Management System (RDMS) data to the Exercise Shift l Superintendent and/or the TSC staff upon request. In order to ensure a level of response commensurate with the exercise objectives, certain radiological parameters may be artificially elevated and will not necessarily reflect the plant dynamic data . 11. Formulation and communication of PARS will be demonstrated by the EOF in accordance with appropriate procedures. 1 3.1-6 l l
i EXERCISE GUIDELINES / EXTENT OF PLAY (continued) l )
- 12. This objective will be demonstrated through a continuous onsite interface between the TSC and OSC where the TSC will monitor and authorize protective actions for site access and exposure control. Security will implement any access control measures. The OSC will implement actions associated with protective equipment requirements, inplant access control, KI administration per Procedure ER-4.3, " Radiation Protection During Emergency Conditions," and exposure control. Offsite personnel protective measures will be controlled from the EOF utilizing Procedure ER-5.2, " Site Perimeter and Offsite Monitoring and Environmental Sampling," if applicable.
Onsite Seabrook Station emergency response personnel shall don appropriate protective clothing. The ability to don and validate proper fitting of respiratory protection equipment will be initially demonstrated and simulated thereafter. For the purposes of this exercise, all personnel who are not clean shaven will be refused respirator protection. OSC personnel will be issued dosimetry. An Exposure Summary Report (ESR) will be available to OSC staff upon calling up FINIS records to review accrued exposures of station staff. Predrill radiation and contamination survey data will be posted on the RCA Control Point. Use of protective clothing, respiratory protection equipment will be demonstrated as required by RCA requirements Administration of KI by offsite emergency workers will be simulated. A station evacuation of non-essential personnel will not be performed during the exercise. All appropriate evacuation alarms and facility notifications will be made in accordance with station procedures. Only designated station staff will respond to the notification process. For this reason, station accountability results will be simulated using a player participation list issued to security orior to the cXerCL66.
- 13. This objective may be demonstrated through a coordinated l effort between the TSC and OSC, as scenario data warrants.
Emergency exposure authorizations will be performed in accordance with Procedure ER-4.3, " Radiation Protection During Emergency Conditions." The EOF will demonstrate offsite emergency exposure authorization as scenario data warrants. 3.1-7 a
. _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _______- ---------------- - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - ~ - - - - - - ~ - - - - ~
i i l L i l EXERCISE GUIDELINES / EXTENT OF PIAY (continued)
- 14. If applicable, the TSC will demonstrate dose assessment capabilities prior to EOF activation. The EOF will )
' demonstrate dose assessment using either the primary or secondary dose projection program.
I
, l 15. This objective will be demonstrated by the EOF. The OSC may direct teams to survey within the bounds of the protected j}
l area, as scenario conditions warrant. The EOF directs ' Offsite Monitoring Teams per Procedure ER-5.2, " Site Perimeter and Offsite Monitoring and Environmental i Sampling." The TSC may direct the OSC to dispatch one (1) Seabrook Station Onsite Monitoring Team for the purpose of testing response time, communications, and monitoring and sampling procedures. The field teams may gather sample material and route those samples to the OSC for analysis. This activity would require implementation of Procedure ER-4.8, " Emergency Onsite Radiological Surveys." It should be noted that offsite monitoring teams will be directed to drive to their assigned locations whereupon field dose rate information will be issued. If the assigned-location is located in a high traffic area, the' teams will-be directed to take air samples in lower traffic areas. Sample data issued will parallel the actual assigned location. 16. Radiological monitoring, sampling and analysis for in-plant and/or onsite activities will be performed in accordance with Procedure ER-3.2, " Operational Support Center Operations." Post Accident Sample Analysis monitoring and sampling activities will be conducted in accordance with series CS0925.0 Chemistry procedures. Simulated radiological, sample collection and analyses data will be provided by controllers upon completion of appropriate actions.
. .c a v --. wouAant s1AA ae cocainea utilizing tne Post Accident Sampling System (PASS). Simulated containment survey cample data will be provided upon request. WRGM and containment l Air sample data will be available for use if samples are !
drawn. Area survey results will be provided by the ' Controller during sample acquisition. Isotopic analysis data will be provided upon demonstration of proper sample preparation and counting delay times. 3.1-8 i
l EXERCISE GUIDELINES / EXTENT OF PIAY ' (continued) l 17. The Control Room, TSC, OSC, EOF, Media Center and JTIC will demonstrate this objective. l 18. The Control Room, TSC, OSC, EOF, Media Center and JTIC will demonstrate this objective. l 19. The Control Room, TSC, OSC, EOF, Media Center, JTIC and the Field Monitoring and Sample Collection Teams will demonstrate this objective. ; j Backup communication systems will be demonstrated only if primary communications systems fail.
- 20. The STED/ SED will demonstrate onsite emergency response control from the Control Room and TSC. The Response Manager will demonstrate overall control of the emergency response effort at the EOF and of the NHY ORO Protective Action Recommendation process until an appropriate transition of responsibility has occurred (to Controllers simulating ORO). ,
k l 21. The Control Room, TSC, OSC, EOF, Media Center and JTIC will ' demonstrate this objective.
- a. INPO Nuclear Network updates will be sent out over the l Nuclear Network in the EOF. They will be clearly marked as drill material.
b. Notification to the Joint Owners shall be made as
} required per ER 3.3. The Joint Owners Liaison should ensure that any scenario time jumps are relayed to the Joint Owners.
c. The Corporate Support Manager should notify NEPEX during the exercise. i d. The Media Center and JTIC will disseminate information in accordance with applicable procedures.
- 22. he Cvntrol noom, aSC anc EOF will demonstrate the ability to transfer appropriate command functions. Command of onsite functions will be demonstrated by the Control Room and the TSC while command of offsite functions will be demonstrated by the EOF.
Control include: Room functions that will transfer to the TSC 3.1-9 l
r' EXERCISE GUIDELINES / EXTENT OF PLAY (continued) l s the decision to and notification of offsite authorities, the formulation and transmittal of PARS, emergency classifications, authorization of exposures in excess of 10 CFR 20 j limits, and ' Public Alert Notification System activation, as necessary TSC functions that will transfer to the EOF are, : i the decision to and notification of offsite authorities, i formulation and transmittal of PARS, and Public Alert Notification System activation, as necessary.
- 23. The Control Room and/or TSC will demonstrate the approval of press releases, if any, which are prepared, reviewed and released in accordance with Procedure ER 3.4, "Seabrook Station News Service Operation."
The EOF will demonstrate preparation, review and approval of l information for transmission to the Media Center. In addition the Media Center and the JTIC will demonstrate dissemination of information to the public in accordance with normal procedures. i l 24. The EOF will demonstrate the ability to provide offsite emergency response organizations with accurate post-accident assessments. Prior to EOF activation, the Control Room and/or the TSC may demonstrate this objective. t
- 25. Communications will be demonstrated among the Control Room, TSC, OSC, EOF and Field Monitoring Teams.
The communication interface between the utility and the New ] Hampshire Yankee Offsite Response Organization, which ' mobilizes the vehicular Alert Notification Svstem t va.N g i atii se uemonstratec; nowever VANS ceployment would not be initiated. , i
- 26. The EOF will demonstrate this objective. Prior to EOF activation, the Control Room and/or TSC may demonstrate this i objective. i 1
The NHY ORO and State of New Hampshire emergency response i organization will be simulated by controllers, 4 3.1-10 l l 1 j
, r
-EXERCISE GUIDELINES /EITENT OF PLAY
- (continued)
- 27. The EOF will. demonstrate the ability to evaluate sample.
analysis. data and/or field measurements, provide appropriate
. protective' action recommendations and interface with'offsite response organizations simulated by the Controller organization, as scenario conditions warrant.. In the event that the EOF sample analysis process is not implemented due to scenario response, a controller'will issue direction to conduct an out-of-sequence demonstration of the sample analysis-process using an exercise prop. Yankee Atomic Electric Company. mobile environmental van and laboratory capability will not be exercised.
p 28. The Media Center will demonstrate the ability to provide timely and accurate information to the media and general public. Press briefings will be conducted using controllers as responding press services. State media center response will not be demonstrated. Outside news service organizations (e.g., UPI or AP) may be contacted (via control cell).
- 29. The rumor control staff will demonstrate the ability to eatablish and operate the rumor control function under the d;rection of the Media Relations / Rumor Control Supervisor.
This function will be established in the Joint Telephone-Information Center (JTIC), located in the Newington Station Modular Office Complex adjacent to the EOF. State rumor control response will not be demonstrated. l 30. The Control Room, TSC, OSC, EOF, Media Center, JTIC and Field Monitoring Teams will demonstrate the ability to conduct a self-critique and identify potential improvement areas. 3.1-11
)
EXERCISE GUIDELINES / EXTENT OF PIAY (continued) PARTICIPAN,TS : A. ERO (1) Full complement for Control Room, TSC,'OSC, EOF, Media
, Center and JTIC.
B. ORO (1) The controllers listed below will simulate various ]
" Command and Control" positions in the ORO in order to provide necessary interfaces for Seabrook Station Response organization to demonstrate objectives.
Available at EOC: NHY Offsite Response Director Accident Assessment Coordinator Technical Advisor NHY Offsite Response EOC Contact NAS Communicator C. N.H. (1) The controllers listed below will simulate various
" Command and Control" positions in the New Hampshire response organization in order to provide necessary interfaces for Seabrook Station Response organization to demonstrate objectives.
Available at State EOC: NHOEM: Director DPHS: Director Available at IFO/ EOF:
. ::C::. .0i m a.Lson DPHS: IFO/ EOF RHTA !
IFO/BOF Coordinator 3.1-12 I
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NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 4.0 EXERCISE CONTROL i i l l C- ._ I
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NEN HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 4.0 XXERCISE CONTROL TABLE OF CONTENTS 4.1 Exercise Control Instructions 4.2 Control Cell Command Center Instructions ) i 4.3 Visitor Observation Rules j 3. 4.4 . Player Instructions 4.5 Controller Organization - I 4.0-1 _ _ - _ _ - - _ - - - - - . - l
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.NEW HAMPSHIRE YANKEE SEABROOK. STATION 1989 GRADED RIERCISE 4.1 EXERCISE CONTROL INSTRUCTIONS 1
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a i: A'. . I)(ERCISE CONTROLLER? INSTRUCTIONS j
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.Allicontrollers:shall1 pre-position themselves at least 301: minutes-prior to H+00:00 hr,LSeptember 27,: 1989 or:as ;
- instructed by.the Exercise: Manager. Controllers will' '
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-wear white;1 identification badges. l
.C 2.- ' Prior to exercise. commencement, all~ controller- -l o
o ' telecommunications willibe tested;tol ensure:satisfa'ctory communications between the Exercise Manager and other-j Lead. Controllers.. Lead Facility. Controllers may be; ] assigned to cordless phones so as to enhance exercise' H f
! Control.
- 3. , The Seabrook Station'1989 Graded Exercise is. designed to )
evaluate the Seabrook;-Station Radiological. Emergency Plan and all, associated: Implementing' Procedures. The j following definitions are designed.to familiarize participants.to. emergency preparedness terminology.in j relation to-controller activities. I
- a. Eggycise l An-exercise is a demonstration of the. Licensee,- I State and Local Organizations integrated emergency' response capabilities, as required by, objectives. I
'It is aftest of'those basic components and elements f designed into the Seabrook Station, State and Local- "
emergency. plans as required. 3 Theseldrills normally. utilize a'eimulation of degraded emergency. con-
'ditions which result in offsite radiological consequences requiring response by offsite authorities. An' evaluation of these response
, . actions identify the adequacy and readiness of plans and participants. b.; Scenario A scenario is a scripted collection'of-time sequenced, simulated events (i.e., operational, radiological meteorological, etc.) designed to promote the demonstration of specific' objectives in an exercise. The scenario'is confidential to all players. Should a compromise of the scenario be' identified, appropriated remedial actions would be taken. 4.1-1
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; Players are'those personnel who' perform specific emergency. response functions in response to scripted iscenario events. Players maintain the responsibility for demonstrating aLproficiency to-required. procedures _and emergency ~ actions while underrevaluation' circumstances ~ . All players must visibly display: identification' badges, whichfare unique to their: emergency. response organization, throughout the course of the exercise.
- d. . Epntroller
- Controllers are those predesignated' personnel who have been assigned responsibility.for providing exercise messages and scenario-specific data to the
. players. Contro11ers'also serve to initiate certain actions .txt ensure continuity in the developing exercise scenario. In addition.a controller may simulate.the response of a player / organization or-member ofothe general public as required to_ provide proper guidance.for demonstration of certain objectives (i.e., playing an injured and possibly
- contaminated person-for demonstration of MS : hospital capabilities). 'This individual may provide
.information.that enhances the driving. force that maintains proper. scenario information flow. All Controllers must visibly display controller badges throughout the course of the exercise.
- e. Evaluator Evaluators are:those predesignated personnel who have been assigned responsibility for documenting and evaluating the actions of the participants'1n. .
response to the developing exercise scenario.- Evaluators provide a source of input to the exercise critique process. In some instances, these
- i. individuals may also be controllers.'All evaluators L must visibly display evaluator badges in addition to identification badges unique to their organization throughout the. course of the exercise.
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V. y 'f.- Observer L Observers"areDpredesignated individuals, employed / contracted by the. utility, federal agencies. or> states to watch a-drill or exercise but who holds no player,s controller'or
+ , Observersfare not1to-ask'. evaluator responsibilities.
questions.of players:or-N impede in"thel player's. response. Observers may. confer, however, with controllers.- All observers Jmust. visibly display observer badges in addition to
- identification badges' unique to their organization throughout the course of the exercise.
- g. Visitor-An individual, not employed / contracted by the utility,:who watches a drill or exercise but who holds no player, controller or evaluator
" responsibilities. 'All visitors.must visibly display visitor badges unique to their organization-throughout the course of the exercise. Visitors observation is also restricted to that as' described in Section 4.3.
- 1. Badae Color-Badges for the previously identified positions are defined by colors listed below:-
- 1. : Controller ' - white
- 2. Evaluator - orange-
- 3. Commonwealth of Massachusetts Response Organization - brown
- 4. Seabrook Station Emergency Response i Organization Players - lime green
- 5. NH Players - gray
- 6. NHY ORO Players blue
- 7. ' Visitors - peach
- 8. Observers - purple a
- 4. Only Controllers can give Players data or instructions.
. As soon as you respond to your emergency location, note who the Controllers are in your area.
- 5. All controllers will comply with instructions from the Exercise Manager and Facility Lead Controllers.
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y , sw s m_ e 2/o - ff ' > h1 . c 6.. LAll; controllers'shall synchronize their' watches to A
' ensure that messages and data are-delivered on time..-
The governing 1 clock is the digital' display in'the
' Simulator Control" Room.- Times on messages andidata #o" ' sheets are' set relative:to actual clock time (real time)?and in someLcases "H"Ltime (start at H+00:00).
7.- ' Controllers:will have copies of the messages controlling. L the progress of the. scenario. EAll messages are.noted with a' number.. Each message number will be prefixed , 4 with>the following letter-identifying the emergency response organization to which it applies. u , SS -Seabrook Station Emergency Response Organization
. In addition,. message-numbers'may.be suffixed with letters in order to-differentiate the following types of-
. messages.
Control Messaaes (no suffix) - Control messages provide information to-the participants-and/or cause the
- participants to take action needed to keep'the exercise-moving smoothly. The Controller will give a.hard copy.
of the control message'to the designated player at the specified. time. Simultaneously, the Controller will provideLthe essential-information verbally. The Controller will-follow through and clarify the message by answering' questions to ensure that the players do not readLextraneous meaning into the message. Controllers shall not provide prompts to players as'to what actions they_should,take. Contingency Messaaes (C) - Contingency messages.will be used only:if players fail to take the major actions expected from the control messages-or other scenario data by'the time designated or warranted. Controllers will.give.the contingency message to'the designated
-player and explain in as much detail as necessary what actions the-players are' expected to perform.
Contingency messages are used to keep the exercise on the scheduled timeline. Sueolementarv Messaaes (S) - Supplementary messages are intended to create problems or actions which do not affect the development of the exercise, but which will provide players with opportunities to resolve situations that might occur as a result of a radiological emergency. They may also be used to provide additional information. 4.1-4
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Simulator Failure Messace (G) - These messages contain information for Simulator Control Room Operators that would normally be provided by the station simulator. These messages would.only be used in the event of a simulator failure. Response MesfA2gg (R) - Response messages are intended to-provide information to players in response to their actions.. The messages.a4 9 used to simulate the actions of individuals who are not participating in the exercise. Typically, response messages are provided to players via telephone and other communications devices.
- 8. Unless otherwise. instructed by the Exercise Director,-
all messages shall be issued at their designated times. Time-related data should be issued only upon request of the appropriate player.
- 9. To simulate the actual audible alarms, those controllers responsible for passing Radiation Data Management System (RDMS) data should announce when a monitor " Alert" or "Hi" alarm is received.. The alarm points are noted on the RDMS data sheets included in Section 10.
Controllers shall not provide information concerning the scenario events or data in advance of the times noted on the messages or data sheets.
- 10. Some players may insist that certain parts of the scenario are unrealistic. Lead Facility Controllers will clarify any questions that may arise during the exercise. Team controllers thould receive guidance from Facility Lead Controllers prior to leaving the facility.
- 11. Each controller shall take detailed notes regarding the progress of the drill and the responses of the exercise players. All notes should be retained for the purpose of preparing a written critique of the exercise. For those purposes, Drill Evaluation Sheets and Evaluation Material will be in controller handouts from the drill manual.
- 12. Controllers may not discuss witn exercise players the proper use of scenario data and/or their expected responses.
- 13. Controllers should ensure that contact between participants and observers (visitors) is minimized.
This may include the establishment of visitor areas in the emergency response facilities. 4.1-5
- 14. Offsite Monitoring Team Controllers should observe the following guidelines: I
- a. Do not issue pocket dosimeter results to team members unless they actually simulate checking their dosimeter.
- b. If the Offsite Monitoring Team stops to take an air samp.le:
- 1. Report dose rate readings as appropriate.
- 2. Note: You shor'i give data only if proper ;
actions are slaalated to take proper readings.
- 3. Proceed to Section 11.0 of this package for definition or technical basis information..
- 15. Due to onsite and offsite data being "AS READ" information, ensure that appropriate gamesmanship on your part is reflected so not to "give away" the idea that there is no plume, i l 16 . . Ensure all communications indicate "This is a drill" at j the start and the end of each message.
- 17. Take no actions that affect non-exercise related operations of the facility.
- 18. If an unsafe condition exists, ignore exercise instructions, take immediate action (s) to restore safe operations and notify the Exercise Director.
- 19. Following the termination of the exercise each Facility Lead Controller shall lead a critique of the exerciso activities at his assigned emergency response facility or with the field team to which he is assigned. This critique should last approximately 30 minutes.
- 20. Prior to submitting the Drill Evaluation Material to the Facility Lead Controller, each controller should determine if player performance meets the criteria established. It is essential that each controller write a summary statement sheet and attach it to the Drill '
Evaluation Material. Categorize your comments as follows: 1) Communications problem; 2) Training j problem; 3) Procedure problem; 4) Equipment problem; and {
- 5) Organizational control problem. j i
All controller material and exercise attendance sheets should be forwarded to the Exercise Director. i l 4.1-6 l
- 21. If the site evacuation horn is sounded, only predesignated personnel on pre-established listings will 3 actually evacuate or go to the Inprocessing Center. All other personnel will NOT respond. -
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h NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 4.2 CONTROL Carm car WD c nTER INSTRUCTIONS l j l 4.2
l ( CONTROT. CELL COMMAND CENTER (CCCC) CONTROLLER INSTRUCTIONS I
- 1. The CCCC in a NHY facility designed to provide those "non-participating" organization functions and interfaces that are required during an exercise to adequately test response 1 activities, through simulated telecommunications or other communications (FAX).
- 2. This facility is located in the second floor of the Onsite
" Stack-a-Shack" and is equipped with telecommunication i equipment capable of establishing a wide variety of ]
connections. I
- 3. CCCC communications equipment will be operated by controllers tasked with " role playing" specific functions or organizations.
- 4. Information may be provided to controllers for dissemination in the form of mini-scenarios. A mini-scenario is'a small- ,
l scale, simulated event, contained within the parameters of the full-scale exercise scenario. It may contain but not be limited to
- a. a sequence of events timeline
- b. supportive technical information pertaining to specific events
- c. identified degrees of simulation
- d. graphics (where necessary)
- e. potential or defined interfaces
- f. expected player responses
- g. intended receivers
- 5. This type of event will be required for those pre-planned scenario events. Section 8.0 will cover those applicable mini-scenarios in depth.
- 6. Any requests for information not previously identified or pre-planned will have to be directed to the facility (CCCC)
Lead Controller. This individual is responsible for managing all " free-play" simulation and will provide final ; resolution (via Exercise Director) on extent of communication. I
- 7. A phone listing for all applicable contact points will be !
provided in either controller packets or facility materials. 1 This will include both player and other controller extensions. NOTE: It is important however, prior to contacting any personnel outside the scope of the scenario to obtain authorization from the Lead Controller. 4.2-1
- 8. Where applicable, control cell controllers will be provided with procedures and/or background information to enable communicators a more effective delivery of correct sequences, methodologies and/or references. It is the responsibility of every controller prior to a drill to obtain a description of required procedures from the facility Lead Controller.
- 9. A collection.of specific control documents will be available for use by controllers to reinforce the validity of control cell outgoing information. These documents may include Letters of Agreement, specific appendices, State and Local plans, procedures, etc.
- 10. All control cell controllers will maintain formal logs and records including:
- a. times notifications were made
- b. position notifications were made to
- c. message content
- d. participant responses / concerns
- e. incoming calls / requests NOTE: The development and maintenance of detailed logs is required to provide Regulatory Agencies adequate evaluatable material in an exercise or drill.
- 11. Proper communication protocol must be utilized during drills or exercises. This is essential to accommodate the proper receipt of such voluminous material. Specific techniques are: '
- a. Deliver short, concise messages, verbose deliveries often confuse the original intent.
- b. Project a commanding tone, but not excited. This will
' enhance message clarity.
- c. Always ensure person receiving message reads back the message to ensure proper receipt.
- d. Always preface and end messages with "This is a drill".
- e. Always direct questions / concerns to the Lead Controller.
- 12. It is planned that all potential control cell contacts be previously identified and developed prior to the drill.
However, because of the " free-play" that is sometimes encouraged by players, situations may exist where spontaneous generation or information is required. Any such circumstances will be forwarded to the Lead Controller for resolution. 4.2-2
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NEW HAMPSHIRE YANKEE y SEABROOK STATION 1989 GRADED RrRRCISE 4.3 VISITOR-OBSERVATION RULES i i I l 1 4.3 '
The following guidelines apply in general to all facilities:
- 1. The visitor must request, in writing, access to the facility at least one week prior to the exercise. Access requests to ERO and NHY ORO facilities should be made to New Hampshire Yankee Emergency Preparedness Department.
- 2. Visitor must consent to comply with security procedures in place at the. facility during the exercise. Violation or infraction of visitor rules will result in the visitor's expulsion from the facility.
- 3. Each facility may designate a " visitor area" within the facility (usually an area of a room marked with rope and/or tape).
- 4. No photography or taping of exercise events by visitors will be permitted.
- 5. Visitors may not question or otherwise interrupt or disturb participants during the course of the exercise.
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- 6. Visitors will provide to the controlling organization, within 1 week, a copy of any notes or observations made during the course of the exercise.
- 7. The number of visitors granted access to a facility may be limited or prohibited due to physical size of the facility.
- 8. In no case will visitors be allowed to travel in any vehicle or other transportation device used during the exercise.
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.NEW HAMPSHIRE YANKEE SEABROOK STATION 1989' GRADED EXERCISE-4.4 PLAYER INSTRUCTIONS l ,
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INFORMATION/ INSTRUCTIONS FOR PLAYERS All key players must read and follow the rules given below. This is important to the success of this exercise. The Seabrook Station Graded Exercise is designed to evaluate the adequacy of the Seabrook Station Radiological Emergency Plan and associated Implementing Procedures. NHY Controllers will input messages at certain times and Controllers at the Control Cell Command Center may represent other non-participants.
- 1. All players should be familiar with the following definitions:
- a. Exercise An exercise is a demonstration of the Licensee, State '
and Local Organizations integrated emergency response capabilities as required by objectives. It is a test of those bhsic components and elements designed into the Seabrook Station, State and Local emergency plans. These drills normally utilize a simulation of emergency conditions which result in offsite radiological consequences requiring response by offsite authorities. An evaluation of these response actions identify the adequacy and readiness of plans and participants.
- b. Scenario A scenario is a scripted collection of time sequenced, simulated events (i.e., operational, radiological meteorological, etc.) designed to promote the demonstration of specific objectives in an exercise.
The scenario is confidential to players. Should a compromise of the scenario be identified, appropriated remedial actions would be taken,
- c. Players l l
Players are those personnel who perform specific emergency response functions in response to scripted scenario events. Players maintain the responsibility for demonstrating a proficiency to required procedures and emergency actions while under evaluation circumstances. All players must visibly display identification badges, which are unique to their emergency response organization, throughout the course of the exercise. 4.4-1 I l L___
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- d. Controller Controllers are those predesignated personnel who have been assigned responsibility for providing exercise messages and scenario-specific data to the players.
Controllers also serve to initiate certain actions to )
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ensure continuity in the developing exercise scenario. In addition a controller may simulate the response of a player / organization or member of the general public as required to provide proper guidance for demonstration of certain objectives (i.e., playing an injured-and possibly contaminated person for demonstration of MS-1 hospital capabilities). This individual may provide information that enhances the driving force that maintains proper scenario information flow. All Controllers must visibly display controller badges throughout the course of the exercise.
- f. Evaluator i
Evaluators are those predesignated personnel who have been assigned responsibility for documenting and evaluating the actions of the participants in response to the developing exercise scenario. Evaluators provide a source of input to the exercise critique process. In some instances, these individuals may also be. controllers. All evaluators must visibly display evaluator badges in addition to identification badges unique to their organization throughout the course of the exercise.
- g. Observer Observers are predesignated individuals, employed /
contracted by the utility, federal agencies, or states to watch a drill or exercise but who holds no player, controller or evaluator responsibilities. Observers are not to ask questions of players or impede in the player's response. Observers may confer, however, with controllers. All observers must visibly display observer badges in addition to identification badges unique to their organization throughout the course of the exercise. 4.4-2
- h. Visitor An individual, not employed / contracted by the utility, who watches a drill or exercise but who holds no player, controller or evaluator responsibilities. All visitors must visibly display visitor badges unique to their organization throughout the course of the exercise.
Visitors observation is also restricted to that as describe,d in Section 4.3.
- i. Badae Color ,
Badges for the previously identified positions are defined by colors listed below:
- 1. Controller - white
- 2. Evaluator - orange
- 3. Commonwealth of Itassachusetts Response Organization -
brown
- 4. Seabrook Station Emergency Response Organization Players - lime green
- 5. NH Players - gray
- 6. NHY ORO Players - blue
- 7. Visitors - peach
- 8. Observers - purple
- 2. REMEMBER - only Controllers can give Players data or instructions.
As soon as you respond to your emergency location, note who the Controllers are in your area.
- 3. Controllers and Evaluators are allowed to ask you questions.
Answer their questions. It is acceptable, when conditions dictate, for you to ask the Controller and/or Evaluator to wait until you complete an urgent task before you answer the question.
- 4. Play out all actions as much as possible in accordance with your emergency procedures, as if it were a real emergency.
Unless authorized by the Controller, you should not simulate q l your actions. 7f authorized to simulate an action, tell the Controller and Evaluators how and when you would actually do them. For your benefit, it is recommended that you play out your actions as much as possible. It is to your advantage to exercise as many of your actions as possible. i 1 4.4-3
s . i ( x k I no p~ l 5 '. . Periodically.think.out. loud, identifying:your key actions ! and decisions to.the. controller, Evaluators and Observers. Thistmay seem artificial, but it will assist in the
. evaluation process and is to-your benefit..
6.- If you are in doubt, ask'your Controller for. clarification. The Controller ~is not allowed to prompt or' coach players during the exercise but is allowed to clarify a piece of data. ,
- 7. If the Controller. intervenes with your play, it is for a.
good reason. Obey yourLController's direction at all times.
.This is essential to the overall success of the exercise.
8.. If you-disagree with your Controller, you can ask him/her to. reconsider or consult with the Facility. Lead Controller or
, Exercise. Manager, asftime permits. You must,'however,
' accept his/her word-as final and proceed.
- 9. .You-musting1 accept any messages / instructions from Evaluators. They.are allowed to ask questions. If they want'to initiate actions,. test your abilities,~or give you
" surprises", they must work through your Controller. This is essential to the overall success of the exercise.
'10 '. T'he Controllers, Evaluators and Observers are;not subject (they are exempt from actinguas if-radiation levels from the emergency exe)rcise are present. Do not let that. confuse you orycause you to act unwisely. .(Must comply with regulations-inplant, hard hat, safety glasses, etc.).
=11. Demonstrate a working knowledge of your emergency operations and procedures. Rernmber proper radio protocol and to preface and end each communications with "This is a drill."
- 12. . Visitors and Observers will not interact with the players.
Do not enter into conversation with the visitors and i Observers.
- 13. ' Personnel safety takes precedence over all other requirements. Follow safety rules, take no unnecessary chances, use all' safeguards and safety equipment provided, and make safety a part of.your responsibility.
14.' In case of accidents or injury, report promptly to your Controller and get first aid or medical help without delay. 1 l,
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BTL : . -, 1 L sg' (M . r .,'J 0 h/ },( 4 (15. . The:following guidelines.should'be' adhered to by field'.
. personnel i
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Players- should minimize arousing or inconveniencing the
-public duringLthe conduct of the drill.
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- 1. ' Field personnel should' minimize'the showing of drill '
related equipment, radios, badges,' hats, dosimetry, y , etc.; L
- 2. 'During-night time conditions, traffic control
{ q personnel should adhere to safety guidelines in y regards1to flashing-lights. ;However, other groups in non-hazardous areas should minimize use of-flashing lights. B. Any' inquiries originating from the general public,.as a' ! result of drill 1 activities, should immediately be passed to the lead controller.of your facility or:the Exercise
. Director, who will notify the appropriate public 1
;information personnel. 1 1
J C. 'Any personnel encountering members of the news media should direct press inquiries to the Emergency News-Manager. ' D. 'In confronted-over your activities by any members of the. general public do not attempt to engage'in arguments or justification of actions. Inform your Lead Facility controller.
- 16. If the site evacuation' horn is sounded, only predesignated personne1'on pre-established listings will actually. evacuate
- or go to.the Inprocessing Center. All other personnel will NOT respond.-
- 17. A critique of the exercise will occur some time after the exercise is terminated. Please provide your input. This will help in the overall Exercise evaluation which will be i held later with the Exercise Director. 3 I
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NEW HAMPSHIRE . DNKEE SEABROOK STATION .l
'J 1989 GRADED RIRRCISE 4.5 CONTROLLER ORGANIZATION l
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b' ?D 1 I. - , b. g.. i l' \ 1 CONTROLLER ORGANIZATION TO BE DEVELOPED AND SUBKITTED AT A IATER DATE i 1 l 4.5-1 2 ___ ______-_-___ _ _ _ _
l i, l NEW HAMPSHIRE YANKEE I SEABROOK STATION l,
. j 1989 GRADED EXERCISE .
{ 2 5.0 NARRATIVE
SUMMARY
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Pev C 7/22/89 , NARRATIVE
SUMMARY
This exercise scenario is based on a small break Loss of Coolant Accident (LOCA) coincident with minor fuel damage. Containment integrity is not breached and there is no appreciable radiological release to the offsite environs. The exercise date is assumed to be Wednesday, September 27,1989. The following Narrative Summary description of response actions is limited to those associated with the New Hampshire Yankee (NHY) Emergenc/ Responsc Organization. , Initial Conditions establish that the statien is operating at 100 percent power with all plant parameters normal and stable. The station has been at or above 90 percent power for 85 days and is in the middle of cycle 1 core life. Safety injection Pump A and Diesel Generator A are tagged out for maintenance and repair. ! The initiating event occurs at 0805 with the failure of the B Diesel Generator Starting Air System. With both diesels inoperable, en unusual Event is declared. The station will remain at 100 percent power while Technical Specification Action Statements are performed to verify the availability of offsite power sources. The Control Room initiates notifications and NHY { Primary Responders report to their assigned locations. It is assumed for simulation purposes that the NHY Offsite Response Organization (ORO) will be executing a Mode 2 response for this ; exercise. The A Diesel Generator is r'! turned to service at 0850. Approximately one hour after the initiating event, a Reactor Coolant System Resistance Temperature Detector (RTD) manifold return line isolation valve develops a bonnet crack which results in a coolant leak to the Containment Building. The leak is not of sufficient magnitude to cause a reactor trip, however, a controlled plant shutdown is commenced. Upon determining that the leak rate exceeds 50 gpm, en Alert is declared. Offsite notifications are made concurrent with the activation of NHY emergency response facilities and the simulated evacuation of non-essential station personnel. Selected non-essential and backup responder personnel report to the onsite Assembly Area at the In-processing Center. At 1100, the RTD manifold isolation valve suffers catastrophic bonnet failure and the subsequent small break LOCA causes a reactor trip and safety injection. Upon entering Emergency Operating Procedure E-1, Loss of Reactor or Secondary Coolant, and determining that continuous Emergency Core Cooling System operation is required, a Site Area Emergency is declared. All operable Engineered Safety Feature components function as designed and no Critical Safety Function experiences a Severe Challenge (Red Path). Following the LOCA, operators begin a plant cooldown and post-LOCA depressur12ation. Based on plant and radiological conditions, and appropriate procedures, NHY will issue no Protective Action Recommendations (PARS) at this time; however, precautionary PARS may be discussed with offsite authorities. Following direction to deactivate emergency response facilities at 1500, exercise play will conclude at 1530 with instruction to begin critique sessions. i 5.0- 1
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NEW HAMPSHIRE YANKEE' SEABROOK STATION 1989 GRADED EXERCISE 6.0 SEQUENCE OF EVENTS
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i NEW HAMPSHIRE YANKEE
. 1 SEABROOK STATION
. 1 1989 GRADED EXERCISE l i
6.1 DETAILED SOENARIO D'iSCRIPTION
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.r REAL ELAPSED .
. MESSAGE TIME _ TIME. DETAILED SCENARIO DESCRIPTION NUMBER
. A. Initial Plant Conditions The exercise date .is assumed to be September 27,1989.
Onsite personnel are limited to the normal weekday
.~ complement. The station is operating at 100 percent '
I power with rod control in the " automatic" mode. The
-i station has been at or above 90 percent power for 85 days and is in the middle of cycle I core life. All plant
, parameters are normal and stable except as noted .%10w.
' Po'sitive Displacement Charging Pump P-128 scheourd for preventative maintenance later this morning and m
.is currently shut down. Centrifugal Charging Pump P-2B is supplying normal charging flow.-
Safety injection Pump P-6A is tagged out for, cleaning and repair of a motor connection and the termination box.
. This work commenced at 1500 yesterday and is scheduled for completion early today. Refer to Mini-Scenario F 1.1 for further information.
Diesel Generator DG-DG-1 A is tagged out for replacement of a local control panel relay. This work commenced at 0430 this morning and maintenance personnel estimate ; completion by 0900 this morning. Refer to Mini-Scenario 8.1.2 for further information. All Technical Specification action statements associated with this tag out have been performed. SIMULATOR:' The Simulator Operator should refer to Mini- Scenario 8.1.2 for repair personnel simulation instructions. One EOF METPAC dose assessment computer has been l removed from the facility for repairs. Refer to ' Mint-Scenario 8.1.3 for further information. B. Initial Meteorolootcal Conditions This exercise will use actual meteorology,1. e., exercise meteorological conditions are the real time, actual meteorological conditions. C. Detailed Scenario Timeline
' 0745 H-00:15 Initial Conditions are provided to Simulator players. SSI 6.1 - 1
( - _- _ - _ _ _ _ _ _
Rev 0 7/22/89 REAL ELAPSED MESSAGE TIME - TIME DETAILED SCENARIO DESCRIPTION NUMBER N_QTE. Message SS2 will transmit initial Conditions to SS2 non-Control Room ERO personnel. fins message should be passed to players as they respond to their assigned facilities. It may also be passed prior to drill
- commencement but in no case before 0745.
N_QTE,: As appropriate, controllers may inform players of the following initial core parameters when requested: Average Core Burnup = 6,600 MW days / metric ton Effective Full Power Days = 173 0800 H + 00: 00 Initial Conditions established; exercise begins. Simulator N/A Lead Controller shall verbally inform the players that the exercise has begun. 0805 H + 00.05 ' Following a normal auto-start, excessive cylinder metal SS3g fatigue leads to.the failure of Diesel Generator DG-DG- 1 B Starting Air Compressor 2B. A cylinder head from tne compressor impacts the inlet line of Starting Air Receiver TK-45C causing a weld failure between the line and the receiver tank. The concurrent failure of the TK-45D inlet backflow check valve,1-DG-Y-69B, allows both Sterting Air Receivers to vent to the B Diesel Generator Room. Refer to Mint-Scenario 8.1.4 for further information. The Control Room receives appropriate low starting air pressure and diesel operability status alarms. SIMUL ATOR: The Simulator Operator shall enter the i appropriate commands to bring in the alarms indicated on Message SS3g. The Control Room would dispatch an Auxiliary Operator (AO) to investigate. This A0 will be simulated by a Simulator Controller. SIMULATOR: A Simulator Controller should refer to Mini- Scenario 8.1.4 for A0 simulation instructions. As needed For exercise purposes, operators will be SS4e directed to maintain the station at 100 percent power should they attempt to initiate a controlled shutdown. (Contigency Message) 0820 H+ 00:20 if not already accomplished, the Shift Superintendent SS5c will be directed to declare an Unusual Event in accordance with Procedure ER 1.1, initiating Condition ! 6b. (Contingency Message) { 6.1 - 2
- - - _ _ - - _ ___ . _ _ _ . l
-Rev 1 9/19/89 REAL- ELAPSED ,
MESSAGE , TIME TIME DETAILED SCENARIO DESCRIPTION NUMBER l A series of media relations and rumor control "S" messages is provided- for controller use following activation of Seabrook Station News Services. . Following the Unusual Event declaration, assigned controllers should refer to the following Mini-Scenarios for simulation and play instructions: NHY ORO - 8.2. I State of New Hampshire - 8.3.1 0850 H + 00:50 Diesel Generator DG-DG-1 A is returned to service. N/A SIMULATOR: As instructed by Mini-Scenario 8.1.2, contact the simulator Unit Shift Supervisor and report the diesel is repaired and ready for restart. 0900 H + 01:00 A valve bonnet crack on the Loop A Resistance SS6g (60) Temperature Detector (RTD) manifold return line isolation valve, RC-V8, results in an 80 gpm leak of reactor coolant to the containment. Tne Control Room receives indications of decreasing pressurizer level and pressure and corresponding increases in containment radiation, sump and humidity levels. A controlled shutdown is initiated shortly thereafter. SIMUL ATOR: Malfunction 21, Delay = 0, Ramp = 0, and Size = .8% As needed For exercise purposes, the plant shutdown rate SS7c will be limited to 20 percent per hour. (Contingency Massage) When needed For exercise purposes, a contingency message will be SS8r utilized to control shift turnover information provided to White Team (second shift) ERO members at the onsite Assembly Area. This message will be passed when deemed appropriate by the assigned controller, l Upon arrival of dose assessment personnel to the E0F, l the assigned dose assessment controller should refer j to Mini-Scenario 8.1.3 for information regarding i the failure of the second EOF METPAC computer. 0920 H+ 01:20 if not alread/ accomplished, the Site Emergency Director SS9c (80) will be oirected to ceclare an Alert in accordance with Procedure ER 1.1, Initiating Condition 1Sb. (Contigency Message) 6.1 - 3 l l l
.Rev 2-
'9/21/89
' 4 ,
' REAL ELAPSED MESSAGE TIME
' TIME' DETAILED SCENARIO DESCRIPTION NUMBER Following the Alert declaration, assigned controllers should refer to the following Mini-Scenarios for simulation 'and play instructions:
Non-State /ORO interfaces - 8.1.6-L d- NHY ORO - 8.2.1 State of New Hampshire - 8.3.1 Following Media Center and Joint Telephone information Center activation, a series of media relations and rumor control "S" messages
~~ ^
is provided for controller use during the duration of the exercise. I100 H + 03:00 RC-V8 suffers catastrophic bonnet. failure resulting in ' SS10g ; (180) ejection of the valve stem. The subsequent small break Loss of Coolant Accident (LOCA) causes a reactor trip and r safety injection. The Control Room receives indications of a sudden, rapid loss of RCS mass and pressure, and corresocnding Increases in containment pressure, temperature, radiation and sump levels. SIMUL. ATOR: Malfunction 21, Delay = 0, Ramp = 1, and ,< Size = 10% Based on current plant and radiological conditions, no Protective Action Recommendations (PARS) are warranted at this time. As neeoed For exercise purposes, a contingency message will be SSIIc utilized to control the NHY PAR. This message will be - passed if a PAR is made which would adversely affect i the conduct of the exercise. (Contingency Mess 0ge) { l120 H + 03:20 if not already accomplished, the Site Emergency Director SSl2c (210) will be directed to declare a Site Area Emergency In accordance with Procedure ER 1.1, Initiating Condition
=
15c. (Contingency Message) L As directed by In order to ensure demonstration of exercise objectives SS13c EOF Lead Controller related to field monitoring and sample analysts activities,- SS14c two messages are provided to direct initiation of these { ( actions. These messages would be used in the event the l players did not direct the performance of the activities. 1400 H + 06:00 NRC Player Controller ( s) arrives at the EOF. Refer to N/A (360) Mini-Scenario 8.1.7 for further information. 6.1 - 4 !
Rev 2 9/21/89 l E REAL ELAPSED MESSAGE l TIME- TIME _ DFTAILED SCENARIO DESCRIPTION NUMBER
]
1 As needed in order to ensure continuity between plant operational SS15cl - parameters and in-plant radiological date, operators will be directed to maintain injection mode core cooling
'should.they attempt to initiate Residual Heat Removal (RHR) shutdown cooling. RHR shutoown cooling will not be allowed as a response action. (Contingency t1essage)
!' 1500 H + 07:00 Emergency response facility managers are now directed SS16 l (420) to begin deactivation and restoration of their respective facilities and organizations.
-p 1530 H + 07:30 Exercise play is terminated as directed by the Lead SS17 (450) Controller. Commence critiques at each emergency response facility and among field team personnel.
1600. H + 08:00 Exercise critique ends; participants dismissed. l i I 6.1 -5
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NEW HAMPSHIRE YANKEE i SEABROOK STATION 1989 GRADED EXERCISE 6.3 NHY ERO EXPECTED PLAYER ACTION
SUMMARY
1 I l l L -' _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ __
I i Rev 1 9/19/69 i NEW HAMPSHIRE YANKEE j EMERGENCY RESPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989 ORADED EXERCISE
GENERAL COMMENT
S
- 1. The source documents for this summary are:
- The Seabrook Station Radiological Emergency Plan (SSREP) .
e The Nuclear Production Emergency Response Program Manual (NPER) 2 Some expected player actions may be simulated. Refer to Section 3.0, Exercise Guidelines, for degrees of simulation and further information. I i
- 6. 3.1 - 1
t , ; Rev 0 7/22/89 NEW HAMPSHIRE YANKEE ENERGENCY RESPONSE ORGANIZAT!ON EXPECTED PLAYER ACTION
SUMMARY
1989 GRADED EXERCISE I. Unusual Event A. Initiatino Condition et 0805 l
- 1. Failure of the B Diesel Generator starting air system which, in conjunction with the tegout of the A Diesel Generator, results in the inability to supply emergency busses E5 and E6 from the diesel generators.
B. Control Room Actions are specified in Procedure ER 1.2, Unusual Event. 1 Shift Superintendent assesses plant conditions and declares en Unusual Event in accordance with Procedure ER 1.1. e Assumes the role of Short Term Emergency Director (STED). e Directs / performs notification of Primcry Responders, the States, the NHY ORO E00 Contact Point, and the NRC. e Turns over Commend and Control responsibilities to Site Emergency Director.
- 2. Unit Shift Supervisor directs SCRO, RO and A0 responses to event.
- Consults relevant Technical Specifications; directs Action Statement (s) compliance actions. )
e Should USS consider a power reduction, e Contingency Message will be used to direct that the station remain et 100% power.
- 3. Control Room Communicator reports to Control Room and performs notifications as directed by the STED.
C. Technical Succort Center
- 1. Not activated at this level. Partial activation is at discretion of Site Emergency Director (SED).
- 2. SED essumes Command and Control responsibilities.
- Directs / performs notification of the States and the NHY OR0.
- 3. Emergency Operations Manager essumes NRC notification responsibility.
- 4. Technical Services Coordinator receives briefing; prepares TSC for activation.
D. Ooeretionel succort Center
- 1. Not activated at this level.
- 2. Radiological Controls Coordinator cells Control Room for briefing.
E. Emeroenev Ooeretions facility
- 1. Not activated at this level.
- 2. Response Menager cells Control Room for briefing.
- 3. EOF Coordinator reports to Control Room; essists with State notifications.
- 6. 3.1 - 2 o
J l> l l Rev 2 9/21/89-NEW HAMPSHIRE YANKEE L- EMER0ENCY RESPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989 GRADED EXERCISE
- 1. Unusual Event (continued)
F. Seaorook Station News Services
- Actions are specified in Procedure ER 3A, Seabrook Station News Services. l
- 1. Emergency News Manager calls Centrol Room for briefing.
- Drafts news release and obtains STED/ SED approval.
e issues news release. 1
.
- Ensures courtesy notifications are made, e.g., State of NH PUC and local area police departments (These calls will be simulated).
G. Guard Island
- 1. Maintain station security.
4 l
- 6. 3.1 - 3
Rev 0 7/22/89 NEW HAMPSHIRE YANKEE c ENERGENCY RESPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989 GRADED EXERCISE II. Alert
~
A. bitiatino Condition et 0905 -
- 1. . Reactor Coolant System Resistance Temperature Detector manifold return line isolation velve develops a bonnet crack resulting in en RCS leek rete exceeding 50 gpm.
B. Control Room
- 1. Shift Superintendent essesses plant conditions and directs e station shutdown.
- Contingency Message may be used to direct station shutdown et 20% per hour.
- 2. Unit Shift Supervisor directs SCRO, R0 and A0 responses to event.
- Consults relevant Technical Specifications.
C. Technical Sucoort Center Actions are specified in Procedure ER 3.1, TSC Operations.
- 1. TSC staff errives, obtains work station packets and activates facility.
e Technical Services Coordinator monitors activation process.
- 2. Site Emergency Director (SED) maintains Commend and Control responsibilities.
e Directs / performs notification of the Stato end the NHY ORO until relieved by the E0F,
- 3. SED directs station response.
- 4. Emergency Operations Manager maintains NRC notifications.
- 5. Health Physics Coordinator assumes dose essessment end PAR responsibility.
e Transfers responsibilities to EOF.
- 6. Station non-essential personnel evacuated (Simulated-Refer to Section 3.0). ,
- 7. Accountability conducted. 1
- 8. Interface with Assembly Area for manpower needs. I
- 9. YNSD responders report and establish work stations.
e Interface with simulated Engineering Support Center established.
- 9. Interfaces established with Control Room and OSC using 3-way phone link D. Ooeretional Succort Center Actions are specified in Procedure ER 3.2, OSC Operations. ;
i
- 1. OSC staff errives, obtains work stetton packets and activates facility. l
- 2. OSC Coordinator assumes Command and Control responsibilities. 1 e Monitors activation process including tag board assignments. ]
- 3. Radiological Controls Coordinator evaluates in-stetton radiological conditions. j e Establishes exposure control measures es required.
l 4. Accountability conducted. 6.3.1 - 4 j i w2_--_._.-_--.-____-_. -_. -
g Rev'I 9/19/89 NEW. HAMPSHIRE YANKEE EMERGENCY RESPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989. GRADED EXERCISE II. Alert (continued) D. Operational Succort Center (continued) 5._ Interfaces established with Control Room and TSC using 3-way phone link.
- 6. Teams formed and dispatched es required.
- Team dispatched to complete repairs on Safety injection Pump P-6A.
- Team dispatched to complete repairs on Diesel Generator DG-DG-18.
- PASS teams may be dispatched.
E. Emeroency 00erations Fecility Actions are specified in Procecure ER 3.3, EOF Operations.
- 1. EOF staff errives, obtains work station pockets and activates facility.
- 2. Response Manager assumes Command and Control responsibilities.
- Directs overall NHY response.
- 3. EOF Coordinator assumes State and NHY ORO notification responsibility.
- Assumes responsibility for PAR determination.
- 4. ECCC drafts press release end initiates coordination actions with controllers
. simulating the Media Center. .i'
- 5. Joint Owner Liaison initiates Jomt Owner contacts.
- 6. DCC Coordinator initiates INPO tetwork releases.
- 7. Security Coordinator directs security actions including EOF eccess
- 8. Offsite Monitoring Coordinator provides direction for Field Monitoring Teams and Sampling Teams.
- 9. Administrative Services Coordinator provides administrative support, additional resources and shift schedules. Interfaces with Assembly Area.
- 10. Radiological assessment activities are established.
- HP-41 used for oose assessment following METPAC failures.
I 1. Internal interfaces established with TSC and simulated Media Center.
- 12. External interfaces established with State of New Hampshire and NHY ORO
- j. contraller organization.
F. Media Center / Joint Telechone Information Center Actions are specified in Procedure ER 3.5, Media Center / Joint Telephone l Information Center.
- 1. Media Center /JTIC staff arrives, obtains work station packets and activates facilities.
- 2. Emergency News Manager assumes Command and Control responsibilities.
- 3. Assistant News Manager monitors activation process.
- 4. Dissemination of press releases at the Media Center.
- 5. Conduct press conferences at the Media Center.
- 6. Establish Rumor Control and Media Relations functions at JTIC.
7.- Internal Interfaces established with EOF.
- 6. 3.1 - 5
Rev 0 7/22/89 l NEW' iPSHIRE YANKEE ENER0ENCY . .JPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989 ORADED EXERCISE II. Alert (continued) F. Media Cente'r/ Joint Telechone Information Center (continued) 8.' External interfaces established with State of New Hampshire and NHY OR0. G. Guard Island
- 1. Conducts Protected Area accountability process.
- 2. Directs evacuation of non-essential station personnel.
- 3. Initiates YAEC pager activation and notifies YAEC security.
i I
- 6. 3.1 - 6 L- -
)
Rev 0 7/22/89 NEW HAMPSHIRE YANKEE EMERGENCY RESPONSE ORGANIZATION EXPECTED PLAYER ACTION
SUMMARY
1989 ORADED EXERCISE lit. Site Area Emergency A. Initiatina Condition et 1100
- 1. Loss of Coolant Accident with Emergency Core Cooling System operation required.
B. Control Room
- 1. Implements appropriate E-Series procedures.
- 2. Commences plant cooldown and post-LOCA depressurtzetion.
C. Technical Sucoort Center Actions are specified in Procedure ER 3.1, TSC Operations.
- 1. Site Emergency Director (SED) decleres Site Area Emergency in accordance with Procedure ER 1.1.
- 2. SED continues to direct station response.
- 3. TSC staff essesses LOCA and related events, and devises mitigating actions.
- 4. Interfaces maintained with Control Room and OSC.
D. Ooeretional Sucoort Center Actions are specified in Procedure ER 3.2, OSC Operations.
- 1. Support end execution of TSC requests.
- Teams formed and dispatched as required.
- e. RCS PASS sample,
- b. Containment air PASS sample.
- 2. Ongoing evaluation of in-station radiological conditions.
- Maintenance of exposure control measures as required.
- 3. Interfaces mainteined with Control Room and TSC.
E. Emercenev Ooerations Fecility Actions are specified in Procedure ER 3.3, EOF Operations.
- 1. Response Manager continues to direct overeil NHY response.
- 2. EOF Coordinator directs maintenance of State and NHY ORO notifications.
- Continues PAR assessments.
- 3. ECCC drafts press release end continues coordination actions with controllers simulating the Media Center.
- 4. Continuance of field monitoring and sampling ectivities.
- 5. Continuance of radiological essessment activities.
- 6. Internal interfaces maintained with TSC and simulated Media Center.
- 6. 3.1 - 7
Rev 2 9/21/89 NEW HAMPSHIRE YANKEE EMERGENCY RESPONSE ORGANIZATION EXPECTED PLAYER' ACTION
SUMMARY
1989 BRADED EXERCISE 111. Site Area Emergency (continued) E. Emeroencv Ooerations Fecility (continued)
- 7. External interfaces maintained with State of New Hampshire ano NHY OR0 controller organization.
F. Media Center / Joint Telechone information Center Actions are specified in Procedure ER 3.5, Media Center / Joint Telephone information Center,
- 1. Emergency News Manager continues to direct emergency public information activities.
- 2. Dissemination of press releases et the Media Center.
- 3. Conduct press conferences at the Media Center.
- 4. Maintain Rumor Contr01 function et JTIC.
- 5. Maintain Media Relations function et JTIC.
- 6. Internal interfaces maintained with EOF.
I G. Guard Island
- 1. Maintenance of station security.
l l
- 6. 3.1 - 8
NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 7.0 MESSAGES 1 l i l l-1 I I l l
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1 NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 71 SEABROOK STATION MESSAGES L21_. ___. _ _ _ _ . _ _ . _ _ _ _ .
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9/20/89-SEABR0' 0K STATION
-EMERGENCY PREPAREDNESS MESSAGE FORM '
I' L " MESSAGE No : SS I - g . TIME: 07.4. 5 T0; Control' Room Personnel FROM: Station loos and instrumentation
. LOCATION: Simulator Control Room
***************************THISISADRILL****************************
The exercise date is assume 1 to be September 27,1989, n Onsite personnel are limited to the normal wcekday complement. The station is operating at 100 percent power with rod control in the " automat!c" mode. The station as been at or above 90 percent power for 85 days and is in the miodle of cycle I core life. All plant parameters are normal and stable except as noted below. Positive Displacement Pump P-128 is scheduled for preventative maintenance later this morning and is currently not operating; Centrifugal Charging Pump P-2B is supplying normal charging flow. Safety injcction Pump P-6A is tagged out for cleaning and repair of a motor connection and the termination box.. This work commenced at 1500 yesterday and is scheduled for completion early , today. L l'
, Following en unsuccessful surveillance test, Diesel Generator DG-DG-1 A was declared inoperable at 0300 this morning. The generator failed to obtain acceptable voltage and frequency readings The diesel was tagged out at 0330 and the ACTION statements of Technical Specification 3.8.1.1 were performed.. Investigation by electricians revealed a faulty field flashing relay located in the local control panel.. A new reiay has been obtained from stores and electricians are currently installing the relay. They estimate that work will be completed and the diesel generator returned to service by 0900 this morning.
See attached shift turnover sheets and work requests for additional station information. Unless otherwise instructed, use actual meteorological data, i. e., exercise meteorological conditfons are the real time, actual meteorological conditions. NOTE: After 0745, this message may be passed to the exercise duty Site Emergency Director and Emergency Operations Manager. They may notify other personnel as they deem appropriate. THIS IS A DRILL 00 NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS
***********************.****************************************** i Page 7.1 - 1
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~ RTE 3 A C3TLL
~ -- CONTROL ROOM RELIEF CHECKLIST-
~
Unit < 'A//- Mode .I_. !7 Offgoing Shift %. - Mid Day Sutng Offgoing SS o n Pre,d .Date Ib!7/dP9 Oncoming SS PART I To be completed by offgoing Unit Shift Supervisor and reviewed by :he oncoming Control Room personnel before assuming the shift. UNIT STATUS flrbs $, se cs'.? Tcwa=g M rnt ee~ es ese.s- 1,o c-e EVOLUTIONS (completed /in progress / planned)
= Dl$ /A Giwo **4 ewr?re v SuleEn i mer- M 7-
- Y~ Ext y ocfr < W 5 ur as esa Me+ A i e b/h / 8 3' uwaru me e-cs., pum . - m-GENERAL INFORMATION Abnormal lineups Off-normal condicions Special instructions /cansideracions
- M pump GA rA c e s-v As>x ci_ mise ,%i o fecarA'- es- cew~< m <w A1' M erer Mm wm 'R s u' b u e~ hAcr M~ 13 ee. ~7"en H
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r i j CONTROL' ROOM. RELIEF CNECKLIST- ! (Continued). .
-PART III. 'To be reviewed or' accomplished by the oncoming ~ shift shortly after .
shift turnover. ' >! 9-4 l SS L*SS - i SCR0! ' RO ! ' i . t- ; Unic Journal- N/A ! N/A'I l l 1- l l l l I Tagging Order Los 1l l l l l' I I I
;.g Chemistry Data and Trends l -
l l l Liquid / Gaseous Discharge < l .I l l Permits I l -- i l' I l. l-Action Statement' Status Log l 1 l 1
;. . Work Reauests l-N/A.I'N/A Bypassec and Inoperaole l l l- l.
'Ecuipment Panel l I I 'l Temporary Modifications Log and [I- j g-Temporarv Setpoint Control Log- I l
. . I I l l l Locked ValveLLog' l l l .
l l
~
l 1 l l l RWP Log l l- l l l , I 1 l l l l Controlled Keys l N/A'I l N/A l N/A l wmrir4TernTNT4T4 ... ..,*,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, ,,,, f PART IV L
' Remarks:
DATE/ TIME / SIGNATURE Offgoing USS. / / Oncoming USS / / OPMM FORM !.-!A Rev. 13 Page 3 of 3
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emm < 7g7 b;f o of, - - > ig? ? Rev 1 9/20/89 7 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
' MESSAGE NO.: SS2 TIME: When Needed (Not before 0745)-
TO: Exercise Plevers
.FROM: Exercise Controllers LOCATION: Where Neeoed '
***************************THISISADRILL****************************
The exercise date is essumed to be September 27,1989. Onsite personnel are limited to the normal weekday complement. The station is operating at 100 percent power and is in the middle of cycle 1 core life.
,. Safety injection Pump P-6A was tagged out yesterday for repair work. It is seneduled to be returned to service early today.
Unless otherwise instructed, use actual meteorological date, i. e., exercise meteorological conditions are the real time, ectual meteorological conoitions.
.........................................**....***..**++.********.
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1-2 x_ _ - - _ - _ _ ._ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ -
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'7/22/*9 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS3g '
TIME: 0805 T0; Control Doom Personnel L FROM; Control Doom instrumentation LOCATION: Simuletor Control Qoom
***************************THISISADRILL***************"*"******"
The following VAS alarms are received: D6601 DG B STARTING AIR PRESSURE LO-LO D6629 DG B TROUBLE F6637 03 B INOP i Additionally, the following Mein Control Board."DG STATUS" light is lit: B DIESEL NOT AVAILABLE i t l
*** ..........*********+..... **........**....*********...........
THIS IS A DQlLL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1 -3 - - _ - - - - - - _ - - _ - _ _ _ _ _ . - . - . _ _ _ - - _ _ _ _ _ - - - . - - - - . - - - - - - - - _ - - - - - _ _ - - - - - - - _ - _ . - - - - . . . J
rev .;
'/::/? 9 -
SEABROOK STATION' EMERGENCY PREPAREDNESS MESSAGE FCRM MESSAGE NO.: SS4c TIME: As Neece] TO: Shtft Superintendent / Unit Shift Suoervisor l FROM: Simuletor Oceretions Controller LOCATION. Simuletor Control Room L
***************************THISISADRILL***********************+++++
Your decision regarding plant shutdown due to the diesel generator failure has been noted. For exercise purposes, maintain station operation et 100 percent cower.
....................** ....................... *....*.....++..+++.
THIS IS A DQllt DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1 -4
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'7/22/89-in ~ g.' )
SEABROOK -STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.i SS5c - TIME: 0820 TO: Shift Su' .erintencent
- 1 FROM: Contro,1 Doom Leed Controller f
LOCATION: Simulator Control Room
* * . . . . . . . . . . . . . . . .. . . . * * * *
- T H I S I S A D R I L L " * " * " " * * * * * * " * " * * + + + "
Events warrant that en UNUSUAL EVENT be declared in accordance with Procecure ER 1.1, Classification of Emergencies, Initiating Conattien 6b. THIS IS A DM DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1-5
Rev 1 l 9/6/89 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM l MESSAGE NO.: SS6g TIME: 0900 T0. Control Rnom Parsonnel FROM: Control Ronm instrumentetinn LOCATION. Simulator Control Room
.********************THISISADRILL****************************
The following annunciators are received . l PZR PRESSURE LO PZR LEVEL LO concurrently with VAS alarm: 4327 PZR PRESSURE LOW AND BU HTRS ON I i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS
................++...**............................. **........+..
Page 7.1 -6
d
- ev 0 I 7/22/59 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS8r TIME: When Neeoed i
!~ TO: AssemSiv Aree Coordineter end Administrative Services Coordinator FROM: Assemelv Aree and EO~ Administrative Controllers LOCATION: Assembiv Aree end Emeroencv Ooeretions Facility
* * * * * * . . . . . . . . . . . . . . .. * * * *
- T H I S I S A D R l L L * * * * * * * * * * * * * * * * * * * * * * * * " "
For exercise purposes and es appropriate to your assigned responsibilities, please observe the following guidelines for shif t staffing and turnover:
- 1. The following facility arrival times for second shift turnover should be provided to appropriate personnel:
Technical Support Center: 1600 Operational Support Center: 1600 Emergency Operations Facility: 1630 Media Center: 1630 1 THIS IS A DQiLL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1 -8
P'
- Rev 0
.7/22/30' i
. SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM.
MESSAGE NO.; SS9c TIME: 0920 T0; Site Emercenev Director 1 FROM: TSC Leae Controller i LOCATION: Technical Succort Center
..******........***......THISISADRILL****************************
Events warrant that en ALERT be ceclared in accorcance with' Procedure ER 1. I' , Classification of Emergencies, Initiating Condition 15b.
..................... ...........................**.+*******.......
THl3 IS A DRILL i DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS
.................................................................. j Page 7.1 -9 '
- _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ )
l Rev 0 -1 7/22/89 SEABROOK STATION-
. EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS10g
' TIME: 1100 T0; Control Room partonnet ,
. )
FROM: Control Acom instrumentetton
- LOCATION: Simulator Control Doom
....***********************THISISADRILL******************"***"*"
The reactor has tripped. Annunciators received in the Control Room include; PZR PRESSURE LO LO (red) TURBINE TRIP PZR PRESSURE LO Si T ACTUATION Si TRAIN A ACTUATION Si TRAIN 8 ACTUATION Cyl TRAIN A ACTUATION CVI TRAIN B ACTUATION FEED WATER ISOLATION Concurrently with the following VAS alarms: 7700 REACTOR TRIP BREAKER A OPEN 7701 REACTOR TRIP BREAKER B OPEN 4596 SI ACTUATION 7906 T SIGNAL ACTUATION 4459 SI ACTUATION PZR PRESS LO 5920 RDMS RADIATION Hl/ EQUIP TROUBLE THIS IS A DRlll DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1- 10 L _ _ - _ _ - _ _ _ - _ _ _ _ _ - _ _ __
* ?ev C 7/22/89 1
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SSI tc TIME: As Needed TO: Resoonse M?necer/ EOF Coorcineter FROM: EOF la_ad Controller LOCAil0N: Emercenev Ooeretions Facility
***************************THISISADRILL"************""*""*""
Your decision regarding Protective Action Recommendations has been noted For exercise purposes, ao not issue a PAR at this time. 1 l l l THIS IS A DRILL l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS y ......*** .......................**............................... Page 7. I- 11 1
Rev 0 7/22/39 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM J: K e-MESSAGE NO.: SS12c TIME: 1120
- TO: Site Emercenev Director
. FROM: TSC Leec Controller
' LOCATION. Technicel Succort Center
**************++++*********THISISADRILL*******************"******+ .;
Events warrant th'at a SITE AREA EMERGENCY be declared in accordance with Procedure ER 1.1, Classification of Emergencies, initiating Conottion 15c. a j THl$ IS A DAILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS ,
.................................................**............... l Page 7.1 - 12
i Rev 1 9/21/89 l SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS13e TIME: As directed EOF Lead Controller T0: Offsite Monitorina Coordinator FROM: EOF Radiolomtal Controller LOCATION: EQE
****************+**********THISISADRILL****************************
i For exercise purposes, direct the field monitoring teams to perform environmental sampling activities. l
...........+....................................... **..........**
NIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1 - 13
I ( Rev 1 j 9/21/89 ' SEABROOK STATION j EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE No.: 5514c TIME: As directed EOF Lead Controller T0: Off?ite Monitorino Coordinator FROM: EOF Radiological Contro11er LOCATION: EfF
***************************THISISADRILL****************************
For exercise purposes, direct the sample analysis personnel to perform sample analysis activities.
.........++++.+............................................*****..
THIS IS 4 DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS Page 7.1 - 14
l r RW 1 9/21/89 SEABROOK STATION s EMERGENCY PREPAREDNESS MESSAGE FORM 1 MESSAGE NO.: SS15c TIME: As Needed l TO: Shift Superintendent / Unit Shift Suoervisor FROM: Simulator Ooerations Controller i LOCATION: Simulator Control Room j
***************************THISISADRILL****************************
Your decision regarding initiation of Residual Heet Removal (RHR) shutdown cooling has f been noted. For exercise purposes, maintain injection mode core cooling until otherwise instructed. l i l I l I \ t l l t THIS IS A DRILL DO NOT INITIATE ACTIONS Aff ECTING STATION OPERATIONS
....*** +***+* ............... .................*** .....*** ..***
Page 7.1 - 15 l 1
Rev 1 9/21/89 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS16 TIME: 1500l T0: ERF lead Menacers FROM: ERF lead Controllers LOCATION: All ERF's
***************************THISISADRILL****************************
Direct the deactivation and restoration of your emergency response fa0llity. l 1 l l l l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS
+++.......***...+....*..**..............+.........*******....*****
Page 7.1- 16
r
- . g 4
Rev't 9/21/89-
,v.'
. . SEABROOK STATION-EMERGENCY PREPAREDNESS MESSAGE FORM -
- MESSAGE NO.: SS17
- TIME: 1530 l TO: Exercise Plevers FROM: Exercise Controllers
. LOCATION: All ERF's and Field Teams
***************************THISISADRILL************************m*
Exercise activities are terminated and a facility critique will now commence. Follow the; instructions of your facility Lead Controller. 1 THIS IS A' Drill DO NOT INITIATE ACTIONS AFFECTING STATION OPERATIONS I Page 7.1- 17
Rev 1. 9/19/89 1 ,- i ( ! NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 7.1.1 MEDIA RELATIONS MESSAGES NOTE: All messages contained in this section are Revision I material.
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-01-MS TIME: 0845+ i TO: SSNS Representative (Call Extension XXXX or XXXX) i FROM: Harold Denton - Amesbury Gazette { LOCATION: Seabrook Station News Service l i
**************************THIS IS A DRILL *************************
NOTE: Controller should wait for first Unusual Event release to be issued to AP/UPI before calling this message. We understand you have declared an Unusual Event. Could you please help me with a few questions?
- 1. What exactly caused the problem? I NOTE: Wait for the representative to discuss the diesel generator before asking the following questions.
- 2. How many diesel generators does Seabrook have?
- 3. What do they supply power to and when are they used?
- 4. Who made the diesel generators?
- 5. Who is this person you mentioned in the release?
Thank the representative and hang up. THIS IS A DRILL DO NO'i INITIATE ACTIONS AFFECTING STATION OPERATION . DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY l DO NOT INITIATE ACTIONS WHICH VIOLATE THE L
*******+*********************************************AW ************ l-89-03-65EX 7.1.1-1 Rev. 1 l
9/20/89 ; { l l 4
l l SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM I MESSAGE NO.: SS-02-MS TIME: 0845+ )
)
TO: SSNS Representative (Call Extension XXXX or XXXX) FROM: Steve Miltenbercer - Exeter Daily News LOCATION: Seabrook Station News Service j i
**************************THIS IS A DRILL *************************
NOTE: Controller should wait for first Unusual Event release to be issued to AP/UPI before calling this message. I have some questions about the Unusual Event.
- 1. Could you tell me more about these diesel generators in terms of what they do?
- 2. Since Seabrook makes its own electricity, why does it need these diesel generators?
- 3. How was the problem detected? I
- 4. Who is fixing (has fixed) the diesel generator? l Thank the representative and hang up.
I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION 00 NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-2 Rev. 1 l 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-03-MS TIME: 0845+ TO: SSNS Representative (Call Extension XXXX or XXXX) FROM: John Nichols - Portsmouth Nicht1v Leader LOCATION: Seabrook Station News Service
**************************THIS IS A DRILL ************************* l l
)
l NOTE: Controller should wait for first Unusual Event release to be issued to AP/UPI before calling this message. I have some questions about the emergency at Seabrook.
- 1. Why do the loss of these diesel generators require an Unusual Event?
- 2. Has any other plant equipment been affected by the diesel problem?
- 3. Were any plant personnel killed or injured when the diesel failed?
- 4. What steps will be taken to ensure this problem doesn't happen again?
Thank the representative and hang up.
*******************************************************+*********
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH IdiD SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW l 89-03-65EX 7.1.1-3 Rev. 1 9/20/89 I __ _________._____m-- _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - - - - - - - - --
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM I MESSAGE NO.: SS-04-MS TIME: 0915-0930 l 1 TO: SSNS Representative (Call Extension XXXX or XXXX) 1 j FROM: Mona Schlabra - Dover Tribune LOCATION: Seabrook Station News Service
**************************THIS IS A DRILL *************************
NOTE: Controller should wait for first Alert release to be issued to AP/UPI before calling this message. Do not call if the SSNS operation has been terminated. I need some information about the accident at the plant.
- 1. What is the nature of the problem?
NOTE: Wait for the representative to discuss the RCS leak before asking the following questions. l
- 2. Is other water being used to replace the water that leaked?
Where is it coming from?
- 3. What can be done to stop.the leak?
- 4. Is the leak in any way related to the earlier problem with the diesel generator?
Thank the representative and hang up. l 1 THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION 00 NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-4 Rev. 1 9/20/89
l: l-SEABROOK STATION l
' EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-05-MS TIME: 1000-1100 TO:
JTIC (Call 1-800-XXX-XXXX)
.FROM: Haverhill Newslett'er - Marlon Smith l-LOCATION: JTIC
**************************THIS IS A DRILL *************************
NOTE: Controller should wait for JTIC activation before calling this message. ; i We.have a UPI dispatch that states you have an alert condition ~at the plant. What.is the reason for the alert? What are plant personnel doing to correct the problem? How.much longer do you expect this problem to continue? Have the states of Massachusetts and New Hampshire been advised? Do you have"an area for reporters to assemble? How do we get there.from here?
. NOTE : .Upon completing the above call, call the Seabrook Station Information Line to determine the available plant status information available through this channel (1-603-XXX-XXXX).
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC IIEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VI THE LAW
******************************************OLATE ***********************
89-03-65EX 7.1.1-5 Rev. 1 l 9/20/89
= ___ __ __ -
.t .
1 SEABROOK STATION I EMERGENCY: PREi'AREDNESS MESSAGE' FORM , MESSAGE NO.: SS-06-MS TIME: 1000-1100 TO: JTIC.(Call 1-8'00-XXX-XXXX)
, .FRCM: Worcester Times Shirley Richardson LOCATION: JTIC-
**************************THIS IS A DRILL ************************* 4 i
Controller should wait for JTIC activation before calling this message. We. understand your emergency status is an alert. Why? Is there any chance the leaking water will reach the swamp next to the plant? Will any tests be done to see if this has happened? Have you been in contact with the Commonwealth of Massachusetts i and, if so, what instructions has he given? Do you have a central location for reporters? Where is it? > l NOTE: Upon completing the above call, call the Seabrook Station Information Line to determine the plant status available information through this channel (1-603-XXX-XXXX). i l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION q DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH IWD SAFETY i DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
*************w***************************************************
89-03-65EX 7.1.1-6 Rev. 1 9/20/89
b o 3EABROOK ' STATION -!
- EMERGHNC'i PREPAREDNESS ' MESSAGE FORM l
I MESSAGE NO.: SS-07-MS TIME:- 1015-1100 4 i 1 i
'TO:-
JTIC (Call 1-800-XXX-XXXX) { FROM: BarbaraERogerc - Portsmouth Tribune LOCATION: JTIC
**************************THIS IS A DRILL *************************
I I have some questions regarding'the emergency at.the plant.
- 1. How much longer will the Unusual Event emergency at Seabrook Station be in effect? ,
- 2. Is there any chance of the situation becoming worse?
- 3. Will Mr. Brown be holding a press conference? ;
- 4. Who's currently in charge at the plant?
- 5. Who is this person that you' referenced in the release?
- 6. How much water has leaked from the reactor?
'~ ************************** ************************************** THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING FUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS W VIOLATE THE LAW
***********************************HICH ******************************
89-03-65EX 7.1.1-7 Rev. 1 9/20/89
P, sy -'
,, j; je SEABROOK. STATION EMERGENCY PREPAREDNESS MESSAGE FORM
' MESSAGE:NO.:
SS-08-MSL, TIME: c1015-1100 .. TO: [ JTIC-(Call.1-800-XXX-XXXX)- .
-FROM Bonnie. Strauss 'WDJV Radio LOCATION: JTIC t
g
**************************THIS IS A DRILL *************************
This is Bonnie Strauss - WDJV Radio in -Boston.- Is the emergency at Seabrook getting worse? What'sthe-danger to the public? How;important'are the diesel generators which.were involved in
. plant safety?
[ - What's'the connection ~between.the diesel generator' failure and y yourt current. problem ~with the' reactor? I need some answers right away. We're about ready to go on the-air with this-and'I need some details. t > THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT' INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTI WHICH VIOLATE THE LAW
.p ******************************ONS ***********************************
L. 89-03-65EX 7.1.1-8 Rev. 1 9/20/89 l t .
l SEABROOK STATION
l EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.:- SS-09-MS ' TIME: 1015-1100 TO: JTIC (CALL 1-800-XXX-XXXX)
FROM: Paul Skiermont - Exeter Chronicle l LOCATION: JTIC
**************************THIS IS A DRILL *************************
i We understand'the emergency is an ALERT.
- 1. Is the plant being shutdown?
- 2. Will the: plant release radiation?
- 3. What do you believe to'be the cause of the reactor coolant system leak?
- 4. Where are you getting water to make up for the water that is leaking out?
- 5. What is this Media Center that a reporter for the Portsmouth Tribune told me about?
i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
***+*************************************************************
89-03-65EX 7.1.1-9 Rev. 1 9/20/89 i 1
i a o , ( tl' id SEABROOK STATION i L EMERGENCY PREPAREDNESS MESSAGE FORM 1 MESSAGE NO.: SS-10-MS TIME: 1030-1100 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Steve Boeddinghaus - Amesbury Reporter LOCATION: JTIC
**************************THIS IS A DRILL *************************
I need'some answers about the emergency at Seabrook.
- 1. .Are plant workers being directed to go home?
- 2. :Who is involved in shutting down the plant?
- 3. Why are the plant workers leaving if you are not recommending anything for the public around the plant?
- 4. How long will it be before all the water leaks out of the reactor? What will happen then?
NOTE: Upon completing the above call, call the Seabrook Station Information Line to determine the available plant status information (1-603-XXX-XXXX). THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-10 Rev. 1 9/20/89 L_____-------_----------_--- - - - - -
SEABROOK STATION f EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: .SS-11-MS TIME: 1030-1100 TO: JTIC (CALL 1-800-XXX-XXXX) 9 FROM: Phil O'Reilly - Millers Nightly Republican LOCATION: JTIC 1'
**************************THIS IS A DRILL *********** **************
Could you please tell me more about the accident at Seabrook?
- 1. How was the problem with the diesels discovered?
- 2. Is there an estimap:.4 as to when it might be corrected?
- 3. Our link with Associated Press went out about an hour and a half ago. Has anything else happened since the Unusual Event emergency.
l' THIS IS A DRILL DO NOT INITIATE ACTIONS AFF1.CTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VI
* * * * * *
- OLATE THE IAW 89-03-65EX i 7.1.1-11 Rev. 1 l 9/20/89 l l
\
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO. SS-12-MS TIME: 1030-1100 TO:
'JTIC (Call 1-800-XXX-XXXX)
FROM: WAS - TV 14, Reporter - Patricia Rice LOCATION: JTIC
**************************THIS IS A DRILL *************************
This is Patricia Rice, WAS-TV 14 Eyewitness News. Could you please comment on the emergency condition at Seabrook. Are you releasing radiation from the plant yet? My videographer and I will be starting for Seabrook within the hour. Can you get us into the plant? Where do you suggest we locate to get some good close-up exterior shots of the plant? Who is the senior most New Hampshire Yankee representative available for un interview? How can I arrange an interview? 1 THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY 1 DO NOT INITIATE ACTI WHICH VIOLATE THE LAW
******************************ONS ***********************************
}
89-03-65EX 7.1.1-12 Rev. 1 1 9/20/89 !
SEABROOK' STATION. EMERGENCY PREPAREDNESS MESSAGE FORM
.. . . l MESSAGE NO.:. .SS-13-MS, TIME:
1045-1100 i TO: JTIC-(Call 1-800-XXX-XXXX)' 1 FROM:' WPAT Radio - Ray Scott . L, LOCATION:, JTIC
**************************THIS s -.
IS A DRILL ************************* 7~. Ray Scott:- WPAT Radio. .Do.you have any projected time-that we can arrange a telephone interview with your Emergency Director. We-haveJarranged a netwerk feed and they are standing by~for the word we are in contaet'.with the Emergency' Director. This interview will go nationwide as part of the developing Seabrook story. i Will you get back to me.before 11:30'with the details'of the
- Emergency Director, interview?-
~
THIS IS A DRILL ~ DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VI THE LAW
******************************************OLATE ***********************
89-03-65EX .7.1.1-13 Rev. 1 9/20/89 i I
.y SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
[. [ MESSAGE NO.: SS-14-MS TIME: 1045-1100 TO: JTIC (Call'1-800-XXX-XXXX) FROM:- Bill Bailey - Hampton Gazette , LOCATION- JTIC i
**************************THIS IS A' DRILL *************************
I l We have word that Seabrook decti:tod an ALERT. Can you help me with the following questions? ' ! i
- 1. What caused the emergency?
- 2. Will radiation escape from the plant?
- 3. Will the plant have to be shutdown to fix the problem?
- 4. How is the water leaking from the reactor being contained?
- 5. Will NRC respond at this level of emergency?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LA
******************************************************W**********
89-03-65EX 7.1.1-14 Rev. 1 9/20/89
j' i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
. MESSAGE NO.: SS-15-MS TIME: 1100-1200 TO: JTIC (Call 1-800-XXX-XXXX)
FROM: Cathy Webb - Haverhill Daily News LOCATION: JTIC-
**************************THIS IS A DRILL *************************
.How critical is this event? How long do you expect this condition'to last?
What-is the danger.to plant workers attempting to correct the problem? Are their lives in danger? What is being done to protect-them? Are any of them being exposed to radiation? I attended a briefing on Seabrook Station's emergency-program earlier in'the year at some location. Is that location operating? THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-15 Rev. 1 9/20/89
._. . _ _ -- _ - --_-- - _ - - - - - _ - - - _ l
s - I i
)
SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM
- MESSAGE NO.: SS-16-MS TIME: 1100-1200 TO: JTIC
~ FROM: . Polly Machias, Newburyport Daily News LOCATION: JTIC '
**************************THIS IS A DRILL *************************
Do you-have any additional information about the emergency? What Federal agencies have been notified? What are their roles in this accident? Do'they have the technical expertise to understand the situation? Will their approval be sought before the plant operates again? THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE L
*****************************************************AW ************
89-03-65EX 7.1.1-16 Rev. 1 9/20/89
( SEABROOK STATION-EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO. SS-17-MS TIME: 1115-1200 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Daniel Taggert - Boston Times LOCATION: JTIC
**************************THIS IS A DRILL *************************
I'm. calling for an update on the situation at Seabrook.
- 1. Do you have any new information?
- 2. What is the estimated damage to the plant?
- 3. Will it be billed to the consumers?
NOTE: Upon completing the above call, call the Seabrook Station Information Line to determine the plant status information (1-603-XXX-XXXX).
***************************************************************** )
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION , DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY l DO NOT INITIATE ACTI j
* * * * * * * * * * * * * * * * *
- e * * * * * ************************************
* * * *
- ONS WHICH VIOIJLTE THE LAW 1 89-03-65EX 7.1.1-17 Rev. 1 ,
9/20/89 l
SEABROOK STATION-EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-18-MS TIME: 1115-1200 TO: JTIC (Call 1-800-XXX-XXXX)
'FROM: Amesbury Daily News Letter - Bill Crawford, Reporter LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Would you speculate that sanotage is a possible answer for all of this activity?
- 2. D7 you have a press briefing area established? Please give i
me directions to the briefing location and are there any special requirements to get in? THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTI WHICH VIOLATE THE LAW
******************************ONS ***********************************
89-03-65EX 7.1.1-18 Rev. 1 9/20/89
t k SEABROOK STATION L EMERGENCY PREPAREDNESS MESSAGE FORM , MESSAGE NO.: SS-19-MS TIME: 1115-1200 TO: JTIC (Call 1-800-XXX-XXXX) FROM:' Ray Scott - WPAT Radio LOCATION: JTIC
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A ' DR IIL * * * * * * * * * * * * * * * * * * * * * * * *
- 1.
Are you absolutely positive no one was injured when the leak occurred? We have a credible source at the plant indicate 2 are dead and 15 are injured. Why can't you. confirm that? i THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTI WHICH VIOLATE THE LAW
******************************ONS ***********************************
89-03-65EX 7.1.1-19 Rev. 1 9/20/89 t
p: L. f SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-20-MS TIME: 1130-1200
.TO: JTIC (Call 1-800-XXX-XXXX)
I FROM: Dan B. Cooper - WPAR Radio LOCATION: JTIC l,
**************************THIS IS A DRILL *************************
- 1. Dan'B. Cooper, WPAR Radio. This last news release indicates things are going to hell in a hand basket up there.
- 2. What is a-Site Area Emergency?
- 3. Have you recommended the evacuation of Seabrook and Salisbury? Why not?
l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-20 Rev. 1 9/20/89
r, SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
'l
)
MESSAGE NO.: SS-21-MS TIME: 1130-1200 l TO: I JTIC (Call 1-800-XXX-XXXX) FROM: Thomas Murley - United Press International LOCATION: JTIC l **************************THIS IS A DRILL ************************* l Could you answer some questions regarding your press release?
- 1. What is being'done to correct the leak and how long will it '!
take?
- 2. Will additional press releases be forthcoming? When?
1 THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY , DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW '
*o************************************************** *************
89-03-65EX 7.1.1-21 Rev. 1 k 9/20/89 f
1 T' L SEABROOK STATION i EMERGENCY PREPAREDNESS MESSAGE ?ORM l MESSAGE NO.: SS-22-MS TIME: 1145-1200 ] TO: JTIC (Call 1-800-XXX-XXXX) FROM: Barbara Rogers - Portsmouth Tribune , i LOCATION: JTIC
**************************THIS IS A DRILL *************************
I have some questions regarding the two emergencies at the plant.
- 1. How much longer will the emergencies at the. plant be in effect?
- 2. What are the chances.of the situation becoming worse?
- 3. Who's currently in charge at the plant?
- 4. How many people are at the plant?
i I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-22 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-23-MS TIME: 1145-1200 TO: JTIC (Call 1-800-XXX-XXXX)~ FROM: Peter Keating - Manchester Globe LOCATION: JTIC l **************************THIS IS A DRILL ************************* \ I'd like some-information about the emergency at Seabrook.
- 1. Is there a possibility of any radiation escaping from the plant?
- 2. Who is checking to see if any radiation leaks from the plant? !
l l i THIS IS A DRILL ' DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIO WHICH VIOLATE THE LAW
*******************************NS **********************************
89-03-65EX 7.1.1-23 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM l- MESSAGE NO.: SS-24-MS TIME: 1145-1200 l' TO: JTIC (Call 1-800-XXX-XXXX) FROM: . Andrew Wyatt --Newburyport Daily Telegram LOCATION: JTIC
**************************THIS IS A DRILL *'************************
I'd like an explanation regarding the events at Seabrook Station.
- 1. What is a Site Area _ Emergency? What. required it to be declared?
- 2. Who authorizes the declaration of an emergency?
- 3. What would have to happen for this to be a General Emergency?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-24 Rev. 1 9/20/89
i i l_ SEABROCK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-25-MS TIME: 1200-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Debbie Tilton - USA Daily - NYC LOCATION: JTIC
**************************THIS IS A DRILL *************************
We are sending a reporter to your next press briefing.
- 1. Which airport is closer to your Media Center, Boston Logan or Manchester?
- 2. Can you provide directions from the airport?
- 3. Has New Hampshire Yankee made any lodging arrangements for
-the press?
- 4. What credentials are required for entry to the Media Center?
I l l l 1 i i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-25 Rev. 1 9/20/09
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE.FOPJi MESSAGE NO,: SS-26-MS TIME: 1200-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Jean Wilson - Danvers Union LOCATION: .JTIC
**************************THIS IS A DRILL *************************
I need some information about the accident at Seabrook Station for our evening edition. Could you give me a recap of the events which have transpired thus'far and tell me what you are doing to contain the radiation? l l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-26 Rev. I L--__-___-_____-_--_-_--
SEABROOK STATION l EMERGENCY PREPAREDNESS. MESSAGE FORM MESSAGE NO.: SS-27-MS TIME: 1200-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Henry Reardon - WNUC TV, New York l LOCATION: JTIC 1 I
**************************THIS IS A DRILL *************************
.I We're preparing a story for our next news break and I need'some f information about the Seabrook accident. 1 I
- 1. Is the plant still operating? I
- 2. What are the federal agencies doing?
3.
~
When do you think the leak will be stopped?
)
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-27 Rev. 1 9/20/89
I SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-28-MS TIME: 1200-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: David Shell - CAB-TV, Portland, OR LOCATION: JTIC
**************************THIS IS A DRILL *************************
We are preparing a story for our 6:00 news and need additional information relating to the Seabrook accident. A. Is the plant still operating? When was it shut down? B. What time do you expect the plant to be completely cooled down? C. Are there high radiation levels inside the Containment? D. We want to do a live telephone feed for 13:30 E.S.D. Will you be available for this feed?
*********************************+*******************************
THIS IS A DRIIJ, DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WH VIOLATE THE LAW
*************************************ICH ****************************
89-03-65EX 7.1.1-28 Rev. 1 9/20/89
1 SEABROOK STATION ) e i EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-29-MS TIME: 1230-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Cathy Clary - Portland Daily Times LOCATION:. JTIC
**************************THIS IS A DRILL *************************
' I'm preparing to send a reporter to your Media Center'and need some information.
- 1. What are the directions. I'm coming from Portland southbound on I-95.
L
- 2. When will your next briefing'be conducted? The one after
.that?
- 3. Who is the spokesperson and what position does he or she hold with New Hampshire Yankee.
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS W VIOLATE THE LAW
***********************************HICH ******************************
89-03-65EX 7.1.1-29 Rev. 1 9/20/89 ) l i
- ~ _ _ - _ . _ - - - - _ . _ . . . -_ b
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-30-MS- TIME: 1230-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Julia Fairchild - WANY-TV, Albany, NY LOCATION: JTIC
**************************THIS IS A DRILL *************************
We're preparing the lead story for the'6 o' clock edition of the I news.
- 1. Do you have an aerial photo of the plant you can wire to us?
- 2. Can you also include photos of the affected area and a brief explanation of the actions being taken to recover from this accident?
NOTE: Upon completing the above call, call the Seabrook Station Information Line to determine the plant status information (1-603-XXX-XXXX). THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-30 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM f_ MESSAGE NO.: SS-31-MS TIME: 1230-1300 TO: JTIC (Call 1-800-XXX-XXXX) FROM Sheila Hurdle - Williamstown (MA) Times LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Would you summarize the events to the present time and the causes of the accident? '
- 2. Has any radiation been detected outside the plant?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTION WHICH VIOLATE THE LAW
********************************S*********************************
89-03-65EX 7.1.1-31 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-32-MS TIME: 1245-1300
!A TO: JTIC (Call 1-800-XXX-XXXX)
FROM: Neil Johnson - KPWR Radio, Winslow, AZ LOCATION: JTIC
**************************THIS IS A DRILL *************************
The wire services report that Seabrook is still at a Site Area Emergency.
- 1. How does this accident compare to Chernobyl?
- 2. How long before the situation is under control?
l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PGBLIC HEALTH AND. SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-32 Rev. 1 9/20/89 _ _ _ _ - - _ - - - - - - l
. lt, -
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE No.: SS-33-MS TIME: 1245-1300 TO: JTIC (Call ~1-800-XXX-XXXX) FROM: Ray Fortney - Burlington Eagle
' LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Do plant _ officials feel that an evacuation is imminent?
l 2. Are all plant safety systems functioning properly now! h THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH IJiD SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-33 Rev. 1 9/20/89
a r-SEABROOK STATION i EMERGE 17CY PREPAREDNESS MESSAGE FORM I MESSAGE NO.: SS-34-MS TIME: 1245-1300 TO: JTIC (Call 1-800-XXX-XXXX) ( FROM: Ed Burke - WANS TV, Albany, NY 1 LOCATION: JTIC'
'**************************THIS IS A DRILL *************************
i I'd like some answers regarding the Seabrook accident.
- 1. What assistance has Seabrook Station received from other nearby nuclear plants?
- 2. What outside engineering firms have been called to provide extra assistance?
- 3. How are'these people getting to the plant?
- 4. Who is monitoring how much radiation plant workers are receiving during the accident?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY j DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW I L ***************************************************************** i l 89-03-65EX 7.1.1-34 Rev. 1 9/20/89 i
~ _ _ - _ - _ _ -
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-35-MS TIME: 1300-1400 TO : . JTIC'(Call 1-800-XXX-XXXX) FROM: Ron Lamb - Milford Herald (PA) LOCATION: JTIC v
**************************THIS IS A DRILL ************************* !
I-have some questions about the news release from Seabrook.
- 1. . What is being done to stop the coolant system leak.
- 2. Are they having any success?
j 1 i I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-35 Rev. 1 9/20/89
I 1 SEABROOK-STATION EMERGENCY PREPAREDNESS MESSAGE FORM !
, MESSAGE NO. SS-36-MS' TIME: 1300-1400 TO:
JTIC-(Call.1-800-XXX-XXXX) FROM: Henry-Smith - Danbury-(CT) Union-Leader LOCATION: JTIC
**************************THIS IS A DRILL *************************
. We are preparing stories for the morning edition and we need information relating to the accident sequence.
- 1. Please summarize the events up to this time. (Don't ask if-press release already generated which provides the summary.)
- 2. Give me the definition of each level of emergency classification.
- 3. Who says the emergency is "over"? What criteria is used?
When do you think the emergency will end? B 1 s THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLAT THE LAW
**********************************************E*******************
89-03-65EX 7.1.1-36 Rev. 1 9/20/89
I.'--' SEABROOK-STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO. SS-37-MS TIME: 1315-1400 TO: JTIC (Call 1- 800-XXX-XXXX) FROM - Wendy Day - WBOZ Radio, Groton, CT LOCATION: JTIC
)
r
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A ' DR IIL* * * * * * * * * * * * * * * * * * * * * * * * * .
- 1. - What states are involved with this emergency?
- 2. Who from the Station emergency response organization interfaces with State personnel?
i THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBT,IC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE L
*****************************************************AW ************
89-03-65EX 7.1.1-37 Rev. 1 9/20/89
i i SEABROOK STATION l t 4
- l. EMERGENCY PREPAREDNESS MESSAGE FORM !
y. , MESSAGE NO.: SS-38-MS TIME: 1315-1400
.TO: JTIC (Call 1-800-XXX-XXXX)
FROM: Sam Adams - Nashua Star LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. I need information relating to those heroic people that are still left at your plant.
- 2. How many people are still there?
- 3. Do you have a method to get them relief supplies and equipment?
- 4. Do you have food on site for these guys?
- 5. How long do they have to work? Who will take over for them?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-38 Rev. 1 9/20/89
f SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO. SS-39-MS TIME: 1315-1400 TO: JTIC (Call 1-800-XXX-XXXX) Shelley Foster - Amityville Bugle
^
FROM: LOCATION: JTIC
**************************THIS IS A DRILL *************************
l-
- 1. How much radiation will the operators have to get before you'-
get them out of the plant?
- 2. Will you select the next group of operators or will they be volunteers?
- 3. Are there other people on the site besides the control room i operators?
l l l l 1 i l d l i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION i DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY ' DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-39 Rev. 1 9/20/89
SEABROOK STATION { EMERGENCY PREPAREDNESS MESSAGE FORM
.l .
^
MESSAGE NO.: SS-40-MS TIME: 1330-1400 { TO: JTIC (Call 1-800-XXX-XXXX)
'FROM: Jesus Miranda - WCAT Radio, NYC i LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. How much longer will the emergency continue?
- 2. When will the plant produce electricity again?
NOTE:- Upon completing the above call, call the Seabrook Station Information Line to determine the plant status information (1-603-XXX-XXXX). L
**********************************e******************************
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIDIATE THE LAW l 89-03-65EX 7.1.1-40 Rev. 1 9/20/89 l
l j 4
.q SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-41-MS' TIME: 1330-1400 TO:
JTIC (Call 1-800-XXX-XXXX) FROM: Susan Oliver - Manchester Union Leader LOCATION: -JTIC
**************************THIS IS A DRILL *************************
l 1. Is-it true that control room operators activated the sirens in New Hampshire?
- 2. How often are the sirens tested? Who tests them?
g THIS IS A DRILL i i DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-41 Rev. 1 9/20/89 j 1
-l , j i
SEABROOK STATION EMERGENCY. PREPAREDNESS MESSAGE FORM MESSAGE NO.:- SS-42-MS TIME:. 1345-1400 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Bill Bonney - Bridgewater (MA) Telegraph LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. ~How much longer does the public need to worry?
- 2. Can this Site Area Emergency escalate?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE I
*********************************,*******************AW ************
89-03-65EX 7.1.1-42 Rev. 1 9/20/89
m_ SEABROOK STATION
-EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-43-MS TIME: 1345-1400 TO: JTIC (Call 1-800-XXX-XXXX)
FROM: Jeff Houseman - Houston Chronicle, Houston, TX LOCATION: JTIC
*************************THIS IS A DRIIL*************************
- 1. As a result of your accident, how many utility people are involved? Please include two categories, one for Seabrook Station and one for the volunteer Offsite Response Organization.
- 2. How can you support 24 hour coverage with the number of people involved?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-43 Rev. 1 9/20/89 L_______ __._____.m_._ - - - - - _ - - - - - - - - - - - - - - -- -
b; [ 'SEAEROOK STATION i. I EMERGENCY PREPAREDNESS MESSAGE FORM I L MESSAGE NO.: SS-44-MS TIME: 1345-1400 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Allison Sterns - Caribou (ME) Leader LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. What is the role of NRC in an emergency?
- 2. Do'the NRC Inspectors at the station take charge of station operations?
_THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAN 89-03-65EX 7.1.1-44 Rev. 1 9/20/89 l
i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM j MESSAGE NO.: SS-45-MS TIME: 1400-1500 TO: JTIC (Call 1-800-XXX-XXXX) 1 FROM: Davis Faircloth - KENO-TV, Reno, NV LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Do you have someone there who can explain the effects of radiation?
- 2. How much will it take to kill people?
- 3. How much radiation is produced by the plant each week?
- 4. Should a release occur, do you have some pills to distribute to the public that will cancel the radiation like the Soviets did?
J
***************************************************************** 4 THIS IS A DRILL I DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY '
DO NOT INITIATE ACTIONS W VIOLATE THE LAW
***********************************HICH
'1 89-03-65EX 7.1.1-45 Rev. 1 9/20/89 )
\
I
f-W SEABROOK STATION 1 l EMERGENCY PREPAREDNESS MESSAGE FORM i MESSAGE'NO.: SS-46-MS TIME: 1400-1500 TO: JTIC'(Call 1-800-XXX-XXXX) FROM: Brenda Young, KCTY Los Angeles, CA LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Would you describe the types of radiation that could be released into the air?
- 2. What is the most hazardous type of radiation to get rid of?
- 3. What are the ways that radiation could escape from the plant?
4. How would a radiation leak be detected and what would be done to stop it? i
)
THIS IS A DRILL ! DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTI WHICH VIOLATE THE LAW
******************************ONS ***********************************
I 89-03-65EX 7.1.1-46 Rev. 1 l 9/20/89
l r SEABROOK STATION
- j. t EMERGENCY PREPAREDNESS MEGSAGE FORK-MESSAGE NO.: SS-47-MS TIME: -1400-1500
-TO:
JTIC (Call 1-800-XXX-XXXX) FROM: Jack Daniels - NBMW,' White Plains, NY LOCATION: JTIC
**************************THIS~IS A DRILL *************************
What pipes? is happening to all that' water that is spilling out of the Are you discharging radioactive water to the salt marsh? How can you prove that?
- 1. What are the plans for cleanup of the reactor building?
2. Who will actually fix the broken pipe and can I speak to him or her?
- 3. Will NRC be involved in this cleanup process?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE IAW 89-03-65EX 7.1.1-47 Rev. 1 9/20/89
}
l i SEABROOK STATION ( 4 EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO': . SS-48-MS TIME: 1400-1500 TO: JTIC (Call 1-800-XXX-XXXX)- FROM: Crystal. Glass, WROC Radio LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. We are informed through our contact from the State that an NRC response team is responding to the station.
***************************************************************** i THIS IS A DRILL {
DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION l DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY l DO NOT INITIATE ACTIONS WHICH VI THE LAW
******************************************OLATE ***********************
89-03-65EX 7.1.1-48 Rev. 1 9/20/89 .
I' r: SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM K MESSAGE NO.: SS-49-MS TIME: 1400-1500 TO: JTIC (Call 1-800-XXX-XXXX) FROM: Marlon Smith - Haverhill Newsletter LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. How does this accident compare to the March 28, 1979 accident at TMI?
- 2. Is there a hydrogen bubble in the Seabrook Station containment building?
- 3. Is there any chance you would be forced to release radiation in a-controlled fashion? Will New Hampshire Yankee inform the public before they do so?
1 i a i l i
***************************************************************** t THIS IS A DRILI.
DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-49 Rev. 1 9/20/89 . _ _ = - _ _ _ _ _ _ _ _ _ _ - _
l
.I i
SEABROOK STATION 6 EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE.NO.: SS-50-MS TIME: 1400-1500 3 TO . JTIC (Call 1-800-XXX-XXXX) FROM: Shirley Richardson - Worcester Times i LOCATION: JTIC
**************************THIS IS A DRILL *************************
1 1. Does'New Hampshire Yankee have insurance to cover damages or [ 1 will the rate payers be stuck balling out the plant, usual? as l 2. What to the will areabe the effect of this accident on electric service residents? , THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE
************************** ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-50 Rev. 1 9/20/89 {
\
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-51-MS TIME: 1400-1500-TO: JTIC-(Call 1-800-XXX-XXXX) FROM: Barbara Rogers - Portsmouth Tribune LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. When can we expect a full report on this accident?
- 2. Can you give me the names of the control room operators and there addresses? We want to interview their family members on the 6:00 news.
- 3. What company insures the plant for this type of accident and can you give me their phone number?
l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WH VIOLATE THE LAW
************************************ICH *****************************
89-03-65EX 7.1.1-51 Rev. 1 9/20/89 )
{ .R i On q.- SEABROOK STATION-EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: -SS-52-MS TIME: 1400-1500 TO:- JTIC (Call 1-800-XXX-XXXX) FROM: Bonnie Strauss - WOJV Radio I e j LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. Can you give me the phone number of Dennis McLain? Can you arrange a live phone link with this Emergency Director?
I'd like to interview him on the air.
- 2. May I interview you live on the air? What is your name? Who do you work for at Seabrook Station? What qualifications do
-you have to perform your emergency job?
- 3. Are there types of information which you are not supposed to tell the-press? Why?
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIO WHICH VIOLATE THE LAW
*******************************NS **********************************
89-03-65EX 7.1.1-52 Rev. 1 9/20/89
=_-_-__-- - -
i SEABROOK' STATION ! EMERGENCY PREPAREDNESS MESSAGE. FORM 1 MESSAGE NO.: SS-53-MS TIME: 1400-1500 l TO: JTIC (Call 1-800-XXX-XXXX) FROM: Paul.Skiermont - Exeter Chronicle LOCATION: JTIC
}
**************************THIS IS A DRILL *************************
1
- 1. I need to talk to someone with a technical background, someone who c 'an better explain just what exactly is going on at the plant. I was a Navy nuclear plant operator and I would like to get a copy of Control Room logs and recordings to look at so I can write a detailed technical article about the accident. Where can I get these?
***************************************************************** i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION j DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY l DO NOT INITIATE ACTIONS WHICH VIDIATE T LAW
*************************************************HE ****************
89-03-65EX 7.1.1-53 Rev. 1 ) 9/20/89 i
t SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORK '
, MESSAGE NO.: 'SS-54-MS TIME: 1400-1500 TO:
JTIC (Call 1-800-XXX-XXXX)- . FROM: Steve Boeddinghaus - Amesbury Reporter LOCATION: JTIC
**************************THIS IS A DRILL *************************
- 1. How do we know that the plant is giving us accurate information? Wouldn't it be in their best interests'to lie to us now and then cover up the problems in the final report?
l They wouldn't admit to any wrong doing anyway, right? I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACT
***************************** IONS ************************************
WHICH VIOLATE THE LAW 89-03-65EX 7.1.1-54 Rev. 1 9/20/89 l . ______ _ _ _ _ l
ri Rev 1 !. 9/19/89 l l l NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE l- !' 7.1.2 RUMOR CONTROL MESSAGES NOTE: All messages containea in this section are Revision 1 materiel.
SEABROOK STATION P EMERGENCY PREPAREDNESS MESSAGE FORM 1 1
)
MESSAGE NO.: SS-01-RC TIME: 1000+- TO: Rumor Control - SS FROM: ~ Tom Lewis - Newfields
~
LOCATION: JTIC
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR II1 * * * * * * * * * * * * * * * * * * * * * * * *
- My neighbor heard that Seabrook Station has an emergency going on because of a diesel generator. Why is this a problem?
Don't you make' electricity there? NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 03-03-G3EX 7.1.2-1 Rev. A 9/20/89
f:,. l SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM
' MESSAGE NO.: . SS-02-RC ~ TIME: 1000+
TO: Rumor Control - SS FROM: Duke Trucker - Newburyport
' LOCATION: SSNS
**************************THIS IS A DRILL *************************
'I heard that your diesel generators are out of order. I thought the plant was nuclear powered! What's going on?
l NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 29-03-55" .;.;-2 Rev. 1 9/20/89
k SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
- MESSAGE.NO.: SS-03-RC TIME: 1000+
TO: Rumor Control - SS FROM: Susan Banks - Hampton Falls LOCATION: JTIC
********************THIS IS A DRILL *************************
NOTE: The controller should call this message in approximately 30 minutes after the Alert has been declared. I'm a desk clerk at Hampton Falls Motor Inn and a guest just told
- me the plant is evacuating. It's not the normal 3 PM shift change time. Could you please tell me what is going on? Do I have to be concerned about an emergency at the plant?
NOTE: CallRumorControlNumbhr 1-800-xxx-xxxx 1
)
THIS IS A DRIIJ, DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
***************************************************************** i 1
03-02-03EX 7.1.2-3 Rev. 1 9/20/89
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y j y SEABROOK STATION q h EMERGENCY PREPAREDNESS MESSAGE FORM I' i !. o ' y p -MESSAGE NO.: SS-04-RC TIME: -1000+ k I TO: ' Rumor Control - SS FROM: Don Daily - Hampton Falls LOCATION: .JTIC 1
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR II1 * * * * * * * * * * * * * * * * * * * * * * * *
- I live next door to a secretary who works at the station.
I heard that' the plant site has been evacuated. Who is left to help manage the accident? NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 33-03-GSEX 7.1.2-4 Rev. i 9/20/89
t c f SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
, MESSAGE NO.: SS-05-RC TIME:- 1000+-
TO: . Rumor Control - SS FROM: Sheldon Davies - Hampton LOCATION: JTIC
-v*************************THIS IS A DRILL *************************
I was out on the marshes when I heard an air horn or siren or something. What did this signal.mean? It scared the hell out of me. NOTE: Call Rumor Control Number 1-800-xxx-xxxx i l THIS IS A DRIII l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION 3 DO NOT. INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY j DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW ] l
?9-02-65EX .1.2-5 Rev. ;
9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM-MESSAGE NO : SS-06-RC TIME: 1000+ ; TO: Rumor Control - SS FROM: George Thompson - Seabrook LOCATION: JTIC
=1
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR IIL * * * * * * * * * * * * * * * * * * * * * * * *
- My. wife works out of there'in the General Office Building (GOB).
Where did you send her? I heard the plant site was being evacuated. NOTE: The caller's wife works for the food service firm that caters the GOB cafeteria. NOTE: Call Rumor Contrcl Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 2 9 - 0 2 5 5 E. .;. -G Rev. 1 9/20/89
SEABROOK STATION
~ EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE 'tJO. : SS-07-RC TIME: 1015+-
TO: Rumor Control - SS FROM: Allan Sidney - Seabrook LOCATION: JTIC
**************************THIS IS A DRILL *************************
Where'did all.the people go that were evacuated from the plant? Did they go down to Haverhill? Are they moving their families out of the area? NOTE: Ca)1 Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS-WHICH VIOLATE THE LAW 99-02-55E% 7.1.2-7 Rev. 1 9/20/89 E ___ _ __ - - - _ - - _ _ - - - - - - - - - _
.]
i r
'l.
i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
.i MESSAGE'NO.: SS-08-RC'. TIME: 1015+
'l TO: Rumor-Control - SS
'FROM: Carol Steele - Stratham LOCATION- JTIC
**************************THIS IS A DRILL *************************
I'm really getting worried about the plant. There are rumors all over the neighborhood that the plant is in more trouble than what's being admitted. Can you tell me what is actually happening and.what I should do? t NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO'NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 03-00-G5EX I.l.2-6 Rev. 1 9/20/89
( -[ , t SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE. FORM MESSAGE NO.: SS-09-RC TIME: 1030+ TO: Rumor Control - SS FROM: Darlene Wilkins - Dover
' LOCATION: JTIC
**************************THIS IS A DRILL *************************
~
I heard that.the Seabrook workers were abandoning the plant and letting the public fend for themselves! Don't you people have any conscience? l l NOTE: Call Rumor Control Number 1-800-xxx-xxxx _THIS IS A DRILL i DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION l DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 29-02-55E.v. .;.: ? ?.e v . 1 9/20/89
i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE'NO.:' .SS-10-RC TIME: 1045+ TO: Rumor Control - SS FROM: Ken Dolan - Newburyport LOCATION: JTIC
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR IIL * * * * * * * * * * * * * * * * * * * * * * * *
- My neighbor told me that the station will dump all this reactor coolant water that's leaking into the marsh. Is that true?
NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW l
***************************************************************** 1 03-03-65EX 7.A.2-10 Rev. 1 9/20/89 l
l i SEABROOK STATION i ENERGENCY PREPAREDNESS MESSAGE FORM j 1 l MESSAGE NO.: SS-11-RC TIME: 1100+ i TO:
~
Rumor Control - SS FROM: Don Martin - Portsmouth LOCATION: JTIC f i l' * * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR IIL * * * * * * * * * * * * * * * * * * * * * * * *
- l My neighbor told me that he just drove by the Station and he saw thousands of people speeding out of the Station. Is this true?
i NOTE: Call Rumor Control Number 1-800-xxx-xxxx l l
********************************************w,*******************
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 1 29 03 55EY. 7.1.0-11 Rev. 1 , 9/20/89 1
.i
[t !s SEABROOK' STATION EMERGENCY ~ PREPAREDNESS MESSAGE FORM
. MESSAGE NO.: SS-12-RC TIME: 1110 TO: Rumor Control - SS FROM: Janet Davis - Hampton Falls 1
LOCATION: JT.IC
**************************THIS IS A DRILL *************************
e Many big black clouds were reported in the immediate area of the station. Is'this radioactive material from this reactor leak? Am I in any danger? l I NOTE: Call Rumor Centrol Nunber 3.-800-xxx-xxxx l l h
***************************************-k*************************
THIS IS A PRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 2o-03-55EY. .1.2-1 nev. 1 9/20/89
- i, SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE'NO.: SS-13-RC TIME: 1115+
TO: Rumor Control - SS
.FROM: Paul Forchetta - Seabrook LOCATION: JTIC
**************************THIS IS A DRILL *************************
I heard a siren sound a few minutes ago. I caught the tail end of a radio broadcast that said something was wrong at Seabrook Station. Are the two events connected? What do I do? This stupid calendar I got in the mail doesn't make any sensel NOTE: Call Rumor Control Number 4 1-800-xxx-xxxx , 1, l i l
**********************************.*****c***************ce*******
l THIS IS A DRIIJ., , l DO NOT INITIATE ACTIONS'AFFECTING STATION OPERATION j } DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY i DO NOT INITIATE ACTIONS WHICH VIDIATE THE LAW 29-22 65EX ~.1.2-12 Rev. 1 9/20/89
SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM f i MESSAGE NO.: SS-14-RC TIME: 1130+ l
'TO: Rumor Control - SS FROM:. Shirley Templeton LOCATION: JTIC
*
- e * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DRIIL * * * * * * * * * * * * * * * * * * * * * * * *
- I heard on the radio-that Seabrook Station is-in a Site' Area Emergency. What does that mean? Are we in any danger?
1:Cf1'E : Call Rumor Control Number 1 -8 0 0-xx v- xxr.x - _
************************et***96*s***s********W*fr******f********w*
THIS IS A DRIIA DO NOT INITIATE ACTIONS AFFECTING STITION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW D-02-05E:: T . . . - 1.; nev. 1 9/20/89 1
SEABROOK STATION EMERGENCY' PREPAREDNESS MESSAGE FORM
' MESSAGE NO.: SS-15-RC TIME: 1130+
TO: Rumor Control - SS
,FROM: Bertha Enoch - Dover LOCATION: JTIC
**************************THIS IS A DRILL *************************
I' heard a rumor that a terrorist was spotted onsite'just before the accident. Did you guys catch the terrorist? 1 NOTE: Call Rumor Control Number . (1 1-800-xxx-xxxx i j l 1 l
.******.**...****.,*******.****,,,,*.***,~....*,,<.**********.****
'1918 IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION j DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW )
j ***************************************************************** 2 9 5 5 EX ' 1.2-15 Rev. 1 9/20/89
e , i L < { l l 1 L i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM { 1 J MESSAGE NO.: SS-16-RC TIME: 1130+
]
TO: Rumor Control - SS FROM: Dave Hall - Hall Communications, Manchester, NH LOCATION: JTIC t
**************************THIS IS A DRILL *************************
I heard about your emergency at Seabrook. I was told.by a
. contractor that worked at your station that the radio system that you use stinks. Listen, if you. guys run short of radios, I got about 50 for sale. Who can I talk to about selling these to Seabrook? You know, you can't have enough radio equipment during an emergency.
NOTE: Call Rumor Control Number j 1-800-xxx~gxyz IEIS IS A DAILL DO NOT INITIATE ACTIONS A.?FECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFUrY ; DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW ' 29 03-55E% .1.2-16 Rev. . 9/20/89
a SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE. FORM
, MESSAGE NO.: SS-17-RC TIME: 1130+-
.TO: Rumor Control - SS FROM: Adam Jones - Greenland LOCATION: JTIC
**************************THIS'IS A DRILL *************************
'I'm a volunteer fire fighter. Do you need any help fighting the reactor fire?-
NOTE: Call Rumor Control Number . i 1-800-xxx-xxxx 3 g - _. - _ _ _ _ _ . . 1 p j I l THIS IS A DRIM j
- j. 00 IiOT INITIATE ACTIONS AFFECTING STATION OTERATICL 1 l DO NOT INITIATE ACTIONS AFFECT 193 PUBLIC HEAI/Fd AND SAFETY i DO.NOT INITIATE ACTIONS WHICH VIOLATL THE LAW
*********************************************,*****************2*
2 9 - 0 2 - 2 E E." .1. Rev. ; 9/20/89
SEABROOK STATION WERGENCY PREPAREDNESS MESSAGE FORM =__ MESSAGE NO.: SS-18-RC TIME: 1130+ TO: Rumor Control - SS FROM: Ivan Bosky - Newfields i i ( LOCATION: JTIC
**************************THIS IS A DRILL *************************
I'm a major PSNH shareholder. Is it true that this incident will have a major impact on the PSNH stock? Should I sell? NOTE: Call Rumor Control Number { 1-800-xxx-xxxx .k IHIS IS A OR_TLL t DO NOT INITIATE ACTIONS AFFECTING ATATION OPERATION E DO NOT INITIATd ACTIONS AFFECTING PUBL'1C HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOIATE THE LAW 23-03-G3EX 7.1.2-16 Aev. - 9/20/89
SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM I-MESSAGE'NO.: SS-19-RC TIME: 1130+
.TO : Rumor Control - SS FROM: Debbie Lewis - Laconia LOCATION: JTIC
**************************THIS IS A DRILL ************************* I My cousin lives in Seabrook and he told me that he saw two guys in a truck roaming the beach area with radios and some type of machines. Are you' people kidding about no release of radioactivity! You would not have people out checking unless there was a problemi t l
r NOTE: Call Rumor Control Number 1-800-xxx-xxxx .
. - - - ~. .
)
++++*=******++**********************************e**o*************
E IS IS A DRILL , ) DO NOT INITIATC ACTIONS AFFECTING CTATION OPERATION l DO NOT INITIATE ACTIONS AFFECTING PUBLIC HUALTH 1mD SAFETY j f DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW '
- j. *****************************************************************
?9-03-65EX 7.1.2-19 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO : SS-20-RC TIME: 1130+ L TO: Rumor Control - SS FROM: Paul Johnson - North Hampton LOCATION: JTIC r '
**************************THIS IS A DRILL *************************
What are you guys using to fight the reactor' fire with? My brother told me that the reactor is-like a big swimming pool and that this leak _is just running into the marshes. Is this true? NOTE: Call Rumor Control Number 1-800-xxx-xxxx l THIS_Ip_A DRTL1_, DO NOT INITIATE ACTIONS API'ECTING STATION OPERATION DO NOT INITIA'IE ACT. TONS AFFECTING PUBLIC HEETH AND SAFETY , DO NOT INITIATE ACTIONS WHICH 57101 ATE THE IAW j 89-03-65EX 7.1.2-20 Rev. 1 9/20/89 a I _ -_ ___ _ _ _ _ 1
i. SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM 1 MESSAGE NO.: SS-21-RC TIME: 1130+ TO: Rumor Control - SS FROM: Diane Currance'- Newington LOCATION: JTIC L * * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR II1 * * * * * * * * * * * * * * * * * * * * * * * *
- 1 What.are you. guys going.to do if your containment springs a-leak?
i l NOTE: Call Rumor Control Number 1-800-xxx-xxxx 1 I
*******.********************** ****,***********s*******************
_TH_I,y __ IS A,, DRIIL . DO NOT INITIATE ACTIONS AFFECTING STATION OPEPATION 00 NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW ; 39-03-65EX 7.1.2-21 Rev. 1 9/20/89
i .. j 1 SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM i t MESSAGE NO.: SS-22-RC TIME: 1130+ j TO: Rumor Control - SS I FROM: John McCall - Kensington j LOCATION: JTIC
**************************THIS IS A DRILL ************************* I 1
It I heard Seabrook got a broken water pipe causing the accident. My. brother is a plumber and he told me that the pipes that you deal with are massive. He says that it's a'special order-to replace them. So your emergency condition will last for years ,. just like TMI. Is this true? NOTE: ! Call Rumor Control Number 1-800-xxx-xxxx l l 4 h
+++*************,cs****.* m **<***,.*********$**.****************** i THIS IF A DRTIL DO NOT INITIATE ACTIONS AFFECTIIM STATIOli OPEFATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HGLTH AND SAFETY 00 NOT INITIATE ACTIONS WfiICF. V
* * * * * *I DIATE TH E IAW 39-03-65EX 7.1.2-22 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS. MESSAGE FORM MESSAGE NO.: 'SS-23-RC- TIME: 1130+ i TO: -Rumor Control SS FROM: Louis'Kyle - Freeport LOCATION: JTIC
**************************THIS IS A DRILL *************************
I'm a freelance photographer. I'd like to take pictures of the emergency responders at the plant if possible. I was told that the Seabrook Station Security staff just beat up a reporter who tried to_get near the plant. Is this true? NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLBTE 7'dE LAW 99-03-65EX 7.1.0-23 Rev. 1 9/20/89
~
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'li
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SEABROOK STATION' I EMERGENCY PREPAREDNESS MESSAGE FORM I
' MESSAGE'NO.: SS-24-RC TIME: 1130+ 1
-l TO: Rumor Control - SS FROM: Joey Tollins j
LOCATION: JTIC
**************************THIS IS A DRILL *************************
What is'being done to protect the wildlife around the plant site? I'm the local Sierra Club representative jn this area. I've been told that Seabrook Station has an 18 wheeler that is parked at the, station specifically to be used to cart away any wildlife that is effected by radiation from the station. Is this true? NOTE: Call Rumor Control Number 1-800-xxx-xxxx i
********************************e********************************
THIS IS A DRIld. DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION i DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEA1.TH AND SAFETY j DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
**********c **************v.***************v**********************
39-03-65EX 7.1.2-24 Rev. 1 9/20/89 1
i .: a. SEABROOK STATION; EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-25-RC TIME: 1130+ TO: Rumor Control - SS FROM: Karen Wood
LOCATION: JTIC
**************************THIS IS A DRILL *************************
Do you think.the accident will get any worse? I have two small children and my husband's out of town. i
' I, NOTE: Call Rumor Control Number 1-800-xxx-xxxx
)
-j i
a
*****+**********************+********************2***************
fBJ} TS A Dit))& DO NOT INITIATE ACTIONS AFFECTING STATION QPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIO WHICH VIOLATE TH3 LAW
*******************************NS *************.******+*************
1 29-02-03EX 7.1.2-25 Rev. i , 9/20/89 !
l' s. h ':, SEABROOK STATION r-EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.:. SS-26-RC TIME: 1130+ TO: Rumor Control - SS FROM: John Lusher - Merrimac LOCATION: JTIC
**************************'HIS IS A DRILL ************************'*
Can any radiation leak out of my electric outlets during the accident? My father told me'that it would. He told me that it ! would come out of the TV if I turned it on. Is this true? NOTE: Act like a kid i NOTE: Call Rumor Control Number 1-800-xxx-xxxx
****v************************************************************
THIS IS A DRII4 DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLAT THE LAW
****4*****************************************E**********s********
29-03-65EX 7.1.2-26 Rev. i 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-27-RC TIME: 1130+ TO: Rumor Control - SS
- FROM: Clyde Smith - Rye
- LOCATION: JTIC
**************************THIS IS A DRILL *************************
Who.is going to pay for the cleanup from this-accident? My father tells me that my electric bill will go up. NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY LO NO'l INITIATE ACTIONS WHICH VIOLATE THE LAW 29-03-65EX 7,1,;_2; Rev. 9/20/89 , l um_~__m_____ _ _ _ _ _ _ - - - - - - -
SEABROOK STATION
' EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-28-RC TIME: 1130+'
TO:
'l Rumor Control - SS FROM: Dave Yaeger - West Point, NY LOCATION: .JTIC r
**************************THIS IS A DRILL *************************
This is Hughes Helicopter in Westpoint, NY. Do you want tc rent any of our helicopters? My father lives in Hampton and he told me that a number of helicopters have been flying over his house since he heard the first news about your accident. I rented
- l. several to GPU back in 1979 for the TMI accident.
NOTE: Call Rumor Control Number 1-800-xxx-xxxx i THIS IS A DRIII l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLAT THE LAW
**********************************************E*******************
29-00-63EX 7.1.2-26 Rev. 1 j 9/20/89
l'. i SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-29-RC TIME: 1130+ TO: Rumor Control - SS FROM: Helen Zinn - Exeter l LOCATION: JTIC
**************************THIS IS A DRILL *************************
Can you smell radiation? I noticed a funny odor outside about a half an-hour ago. NOTE: Call Rumor Control Number 1-800-xxx-xxxx
***************************************w*************************
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION l DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFET" DO NOT INITIATE ACTIONS WHICH VIOLATE THE IAW 89-03-65EX 7.1.2-29 Rev. 1 9/20/89
\
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-30-RC TIME: 1130+ TO:- Rumor Control - SS FROM: Dale Mayburry - Greenland LOCATION: JTIC L
* * * * * * * * * * * * * * * * * * * * * * * * *
- THI S I S A DR II1 * * * * * * * * * * * * * * * * * * * * * * * *
- I heard that this accident was caused by a terrorist. Why did i you allow a terrorist into the plant?
NOTE: Call Rumor Control Number 1-800-xxx-xxxx
********=********************************************************
THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIO.NS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-30 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-31-RC TIME: 1130+ TO: Rumor Control - SS l FROM:- Henry Tynes - Hampton Falls LOCATION: JTIC'
* * * * * * * * * * * * * * * * * * * * * * * * *
- THI S I S A DRIIJ.* * * * * * * * * * * * * * * * * * * * * * * *
- I heard.that the reactor has caught on fire like that Russian reactor. Do you guys need any help fighting the fire?
l l NOTE: Call Rumor Control Number l 1-800-xxx-xxxx l THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIDIATE THE LAW 89-03-65EX 7.1.2-31 Rev. 1 9/20/89
ha SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-32-RC TIME: 1130+ TO : ' Rumor Control - SS FROM: Denise Shepard - Hampton l LOCATION: JTIC
**************************THIS IS A DRILL *************************
I'm 8 months. pregnant and I want'to know if there is anything I need to do to protect my baby. I've got friends in Raymond. Should-I move my family to Raymond? Is that far enough away to
. be safe? My mother-in-law in Hampton Falls tells me that everything is okay.
NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION l DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
***************************************************************** I 89-03-65EX 7.1.2-32 Rev. 1 9/20/89
LI , .{ s I L
-SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.:. SS-33-RC TIME: 1130+
TO: Rumor Control - SS 1 FROM- Michelle Wiggins - Lowell Resident LOCATION: JTIC
************* ,***********THIS IS A DRILL *************************
I'm a' nurse in Lowell and I heard on TV that the plant had a LOCA. I did hear all the report. I asked my roommate what a LOCA was. -She told me that it was a Lethal Offsite Coolant Accident. Is this true? NOTE: Call Rumor Control Number 1-800-xxx-xxxx l i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
***************************************************************** j
\
89-03-65EX 7.1.2-33 Rev. 1 9/20/89 {
o ., t j j SEABROOK STATION l EMERGENCY PREPAREDNESS MESSAGE FORM i 4 MESSAGE NO.: SS-34-RC TIME: 1130+ TO: Rumor Control - SS l FROM: Milton O'Brien - East Kingston Resident LOCATION: JTIC-
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR II1* * * * * * * * * * * * * * * * * * * * * * * *
- I just got a call from my wife about the accident at Seabrook.
She's at home.in East Kingston and I am at work here in Durham. She-wants me to come home and get her and the kids out of there. Is there a chance ~they are in danger? I've heard all the reasons of why the plant is safe, but I don't want my family in any danger either. What should I do? NOTE: Call Rumor Control Number 1-800-xxx-xxxx l
***************************************************************** t THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION )
DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-34 Rev. 1 9/20/89 -_L_2_.---__-___-_---__._
SEhBROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-35-RC TIME: 1130+ TO: Rumor Control - SS FROM: Sue Davis - Danvers LOCATION: JTIC
**************************THIS IS A DRILL *************************
My neighbor-told me that this accident was caused by sabotage. She said that a friend of her husband's works out at the plant I and that they were looking for the' saboteurs. NOTE: Call Rumor Control Number 1-800-xxx-xxxx l
***************************************************************** I THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-35 Rev. 1 9/20/89
- l SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE. FORK !
MESSAGE NO.: 'SS-36-RC TIME: 1130+ TO: Rumor Control - SS FROM: Angela' Carter - Seabrook Resident LOCATION: JTIC
**************************THIS IS A DRILL *************************
Hello, Rumor Control?- Hi, this is Angela Carter. I just heard in'the. grocery store that because of the bad welding done ct Seabrook-Station you now have uncontrollable radiation spewing out of the' plant. Is this true? uummudr-hemmmmemy NOTE: Call Rumor Control Number L 1-800-xxx-xxxx J I s
)
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION : DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW i ***************************************************************** 89-03-65EX 7.1.2-36 Rev. 1 9/20/89 L_____---_--- - -
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-37 RC TIME: 1130+ TO: Rumor Control - SS FROM: Constance Davis .Hampton Falls LOCATION: JTIC l
**************************THIS IS A DRILL *************************
Before you started up that plant you showed up with all your facts about government. inspections'and being able to withstand plane crashes. How do you explain this accident? Were the reports of poor. workmanship due to drunk drug-crazed craftsman true? l f 1. t NOTE: Call Rumor Control Number j- 1-800-xxx-xxxx l I 1 THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY i DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-37 Rev. 1 9/20/89
4 SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-38-RC TIME: 1130+ TO: Rumor Control - SS FROM: Cynthia Snodgrass - Seabrook' Resident-LOCATION: JTIC
**************************THIS IS A DRILL *************************
I just heard that a big pipe with radiation in it broke at the plant. I live in Seabrook and I am six months pregnant. .Is it. safe for me to stay.here? Will I have my baby prematurely because I've had. contact with the radiation? ' L
}
NOTCd Call Rurx>r Control Number ; 1-800-xxx-xxxx j !: 1 l i THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING' STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE
************************** ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-38 Rev. 1 9/20/89
SEABROOK' STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.:. SS-39-RC TIME: 1130+ TO: Rumor Control - SS FROM: Allan Carter - Hampton Falls
. LOCATION: JTIC
**************************THIS IS A DRILL *************************
My father told me that Seabrook Station has to pay all my expenses if I leave my home'. I want to get my family to a safe place.before that plant really goes berserk. Can I bill NHY for all my expenses and if anything happens to my house while I'm gone can I sue'you? NOTE: Call Ramer Control Numter 1-800-xxx-xxxx [ s .-- - , . ,_ l L I l ***************************************************************** THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION
- - DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT' INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-39 Rev. 1 9/20/89
, i
.)
SEABROOK' STATION
, EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-40-RC TIME: '1130+
TO: Rumor Control - SS- q
. J 4
FROM: Joanne Merchant - Stratham, NH' LOCATION: JTIC
**************************THIS IS A DRILL *************************
- I monitor the local area police and fire nets. I heard 3 reports of-robberies in the Seacoast area since'the emergency announcement. Does:this type of activity happen every time a nuclear emergency happens?
l NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW i **********************w ***************************************** , 89-03-65EX 7.1.2-40 Rev. 1 9/20/89 L .
p s , SEABROOK STATION v, ) EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: .SS-41-RC TIME: 1130+ TO: Rumor Control - SS FROM: Robert Barnes - Hampton Resident LOCATION: JTIC-
**************************THIS IS A DRILL *************************
WPAR radio has been reporting that Nuke Plant is in serious trouble but you guys are covering up the problem. What's' going l on or are you going to keep covering up the problem at the plant? NOTE: Call Rumor Control Number 1-800-xxx-xxxx
+****************************************************************
THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY J DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-41 Rev. 1 9/20/89
p i I SEABROOK STATION-EMERGENCY PREPAREDNESS MESSAGE FORM i i MESSAGE NO.: SS-42-RC TIME: 1130+ TO: Rumor Control - SS ( FROM: Lyle Davis - Newbury LOCATION: JTIC
**************************THIS IS A DRILL *************************
I'm trying to find out where I can get some radiation pills. 'I heard the Station.is passing them out to their emergency response people. NOTE: Call Rumor Control Number o 1-800-xxx-xxxx l l l ***************************************************************** THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW
***********************************************4 ****************
89-03-65EE 7.1.2-42 Rev. 1 9/20/89
p l I I SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM
-l I
MESSAGE NO.: SS-43-RC TIME: 1130+ TO: Rumor Control - SS FROM: Jeff Dawson - Exeter Resident LOCATION: JTIC
* * * * * * * * * * * * * * * * * * * * * * * * *
- TH I S I S A DR IIJ * * * * * * * * * * * * * * * * * * * * * * * *
- Hello, this is Jeff Dawson. I was just talking to my son Lenny who works down at the plant. Maybe you know him. He's a fire watcher. He told me that the radiation levels are very high at the plant. That's why everybody except two or three volunteers had to leave. Is'this true?
NOTE: Call Rumor Control Number 1-800-xxx-xxxx i
*********************+******************************************* !
THIS IS A DRILL . DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION I DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOIATE
************************************************THEIAW *****************
89-03-65Ex 7.1.2-43 Rev. 1 9/20/89
7 -- ., i l l
.SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM L
. MESSAGE NO.: SS-44-RC TIME: 1130+
TO: Rumor Control - SS FROM: John Kodak - Amesbury Resident LOCATION: JTIC
**************************THIS IS A DRILL *************************
s My' friend who works at the plant just telephoned and said the plant is now really'out of control. Is this true and what should we do now? NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-44 Rev. 1 9/20/89
SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-45-RC TIME: 1130+ TO: Rumor Control - SS FROM: Nancy Donegan-- Raymond Resident LOCATION: JTIC
**************************THIS IS A DRILL *************************
i-Yes could you tell me what measures are being taken to protect the workers at Seabrook Station? Are the people working on the problem in any danger of getting radiation exposure? My son works down there you know. I told him it was a dangerous place to work. But he wouldn't listen. I have not been able to reach him. Did Seabrook Station keep him at the plant to support the emergency response efforts? l CONTROLLER NOTE: MRS. DONEGAN'S SON IS A CARPENTER. NOTE: Call Rumor Control Number 1-800-xxx-xxxx
- I THIS IS A DRILL l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION ,
DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY l DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-45 Rev. 1 9/20/89 j
SEABROOK STATION f EMERGENCY PREPAREDNESS MESSAGE FORM MESSAGE NO.: SS-46-RC TIME: 1130+ TO: Rumor Control - SS FROM: Bea Goode - Portsmouth LOCATION: JTIC
**************************THIS IS A DRILL *************************
~
I'm calling to find out if you people are going to be able to get the plant back in operation. My father tells me Seabrook Station has to pay any increased electric rate cost that area residents might experience due the unavailability of the Seabrook Station power. Is this true? NOTE: Call Rumor Control Number 1-800-xxx-xxxx 3 THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS.WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-46 Rev. 1 9/20/89
1 SEABROOK. STATION EMERGENCY PREPAREDNESS MESSAGE FORM' k MESSAGE NO.: SS-47-RC TIME: 1130+ TO: Rumor Control - SS FROM: Calvin Taylor - North Hampton 4 LOCATION: JTIC y l **************************THIS IS A DRILL ************************* Hello, this is Calvin Taylor of North Hampton. I understand the nuke plant is leaking radiation. Could.you tell me how long before your so-called qualified technicians fix the leak? My neighbor told us that this Site Area condition means long term delays in restoring the plant back to full operation. Is this true? l NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS.WHICH VIOLATE THE LAW
*********+*******************************************************
89-03-65EX 7.1.2-47 Rev. 1 9/20/89
i o U , SEABROOK STATION
^ EMERGENCY PREPAREDNESS MESSAGE FORM 4 9 i , i MESSAGE NO.: SS-48-RC . TIME: 1130+ )
I TO: ' Rumor Control - SS I FROM: John Hanson -' Dover Resident Pharmacy Store LOCATION: JTIC L
'**************************THIS IS A DRILL *************************
This is John Hanson of Dover Pharmacy. I've been having all kinds of people coming in here asking for anti-radiation pills'. What's the story, is there such a thing or just some hoax?. 1 I i NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW l J 89-03-65EX 7.1.2-48 Rev. 1 9/20/89 L _ __ ____-.
I m SEABROOK STATION j
-4 EMERGENCY PREPAREDNESS' MESSAGE FORM -
MESSAGE NO.: SS-49-RC TIME: 1130+ TO: Rumor' Control' 'SS FROM: Pauline Dennison .Seabrook Resident - LOCATION: 'JTIC'
**************************THIS IS'A DRILL *************************
'My homeowners insurance says they won't pay me a dime if radiation gets on my house. They told me that I should sue New Hampshire Yankee. Who should my lawyer contact first?
NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRIII DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE IAW 89-03-65EX 7.1.2-49 Rev. 1 ) 9/20/89 l 1 i
l SEABROOK STATION EMERGENCY PREPAREDNESS MESSAGE FORM I MESSAGE NO.: SS-50-RC TIME: 1130+ TO: Rumor Control - SS FROM: Charles Ruth - Boston LOCATION: JTIC
**************************THIS IS A DRILL *************************
I understand that the plant really has a meltdown going on now. How much radiation is being released? Which way is the wind blowing and how soon is the cloud expected to be down here? 1 NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL l DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION ' DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW j
***************************************************************** l l
.89-03-65EX 7.1.2-50 Rev. 1 1 9/20/89
b t '
,. ,. 14 M
, 'SEABROOK STATION EMERGENCY PREPAREDNESS' MESSAGE FORK.
l
' MESSAGE NO.:' SS-51-RC TIME: :1130+
TO': ' Rumor Control - SS FROM: Ted.Baer'- Merrimac LOCATION: JTIC--
**************************THIS IS A DRILL *************************
How in the world can someone allow this to happen?- What' happened to all the safety systems you have.there? How much time do I have before the, radiation is released and gets here? I L. , NOTE: Call Rumor Control Number ; 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW 89-03-65EX 7.1.2-51 Rev. 1 L 9/20/89 l L___-____-____ - _ _ _ _ _ _
. I SEABROOK STATION )
EMERGENCY PREPAREDNESS MESSAGE FORM ; i i MESSAGE _NO.:- SS-52-RC. TIME: 1130+ l TO: Rumor Control - SS ) FROM: Acme Fire Supplies - Dover LOCATION: JTIC
**************************THIS IS A DRILL *************************
Heard you guys are having a fire at'the nuke. We have 2 tons of fire suppressant for sale if you need it. NOTE: Call Rumor Control Number 1-800-xxx-xxxx THIS IS A DRILL DO NOT INITIATE ACTIONS AFFECTING STATION OPERATION DO NOT INITIATE ACTIONS AFFECTING PUBLIC HEALTH AND SAFETY DO NOT INITIATE ACTIONS WHICH VIOLATE THE LAW l' i 89-03-65EX 7.1.2-52 Rev. 1 l 9/20/89
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1 Rev 0
- 7/22/89'
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MINI-SCENARIO 8.1.1
)
SAFETY INJECTION PUMP P-6A
~
This pump was tagged out to M. Brambilla at.1500 on September 26,1989 to investigate , suspect meggar readings recorded during a preventative maintenance test. Electricians Installed l a ground truck in the associated breaker cubicle (Bus ES, Node 1-A56) prior to preceding to the pump.
^
inspections at the motor revealed excessive moisture condensation on the inside of the motor termination box. The condensation was due to a failed motor heater' lead. A large nick was also discovered on the Phase C Raychem motor connection. The Phase C motor connection was de-terminated and cleaned as was the motor termination box. The motor heater was replaced. Megger checks of the pump motor were. acceptable. The above work was completed prior to the ALERT declaration. An Emergency Repair Team may be dispatched to complete pump repairs. The assigned controller should note what measures are teken to assure the safety of the repair team. The following items are at the work scene:
- 1. Tool box and tools
- 2. New Raychem connection and Raychem heat gun 3, Electrical test equipment
- 4. Work requests, procedures and prints !
Remaining work to return the pump to service includes:
- 1. Re-terminate and torque Phase C motor lead (= 15 minutes)
- 2. Install Raychem kit on Phase C motor lead (= 60 minutes)
' 3. Perform meggar checks at Bus ES, Node 1-A56 (= 60 minutes)
- 4. Lift tags and rack in breaker at Node 1-A56 (= 15 minutes)
. The pump should not be returned to service before 1300.
l i l Pege 8.1 -1
WORK REOLTST SECTION I - ISTTIATION 7 b-MG ^f. sr p- 0 A lC MP NEM ggeg L <c4 on p_ 4 t{q}g o ogig p blT LOCATION N lhlT DOC: fYSgE. lT FAILURE! WORK REQUESTED [n g,e sh ate F a'i le d th e4je r rcFob. 5 ORIG k Cyg /p (DATE 1/.ts/r9 plSCOVERY STATUS l & { .. L l EFFEG ON PLANT 4t i EXTENSION '// SS l DEPT. % b FECT ON 5YSTEM lAl f "l FAILURE DETECTION IO} l SECTION II - APPROV AL PRIORITY l M.E.R. 3gp . DENT / d # /j'[##I SECTION III - EVALUATIONIPLANNING LEAD DEFT. TECHNCAL REOLlREMt.NTS SAFETY RELATED i V 6 SECURITY I N i ASME SEGON XI iw ASSIST DEPT. FIRE PROTECTION l 9 l EQUIP. QUALIFICATION l V i 1E ASSOCIATED 1v WRD - ~" SEISMIC i yi INSERVICE TESTING l $( l B31.1 UPGRADE Ip PROOR A\t HEOllREMENTS P rocacures/ O rawines (WELDeS PEC. TRAN . gg g
,g7g373 M S O ft3 09 M SofN.OI I JESCRIFUON OF WORK /PRECAUEONS
&n ov a, tvichot~ tr m;nho^ covQr inJes D anck dekecxA , us,4 M k q. r, as o < c asa r,y.
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SCHEDULE 1MPACT CODE OlOlO I UNIT CaARcE NuMsER ENa wEER i % f & *t a cATE r/.ri/sy / 2 o o o 01 o al 6 \/ l b) COMBUSTIBLE CONFWED SPACE TACCING NO. : ! T EGN. SOURCE PERMIT jy MAT't PERMIT N ENTRY PERMIT N itWP /SRWP NO. : Y l MAT *L PRESTAGED ALARA ly lHK REQTS FORM jy HK CLOSEOUT FORM ;y EST. TIME OtJT OF SERVICE * /7 fcura EST. MANHOURS a (O ! QC SIGNATURE Mh4 NuuriQC PRIORTO START y HOLD POINTS lAf DATE g/,gg/fp l RESPONSIBLE PLANNER ////c/ 7 / //h M MA 3 ;A c- '
Rev C 7/22/69 MINI-SCENARIO 8.1.2 DIESEL GENERATOR A STATIC EXCITER RELAY FAILURE All aspects of this Mini-Scenario will be simulated by designated controller personnel Diesel Generator DG-DG-1 A was tagged out to L. Felch at 0330 on September 27,1989 to investigate unacceptable voltage and frequency readings recoroed during a surveillance test. l Generator rated voltage and frequency was briefly obtained but quickly ecayed off and could not I be recovered.' The engine was then shut down end tagged. The following events occurred at the indicated times: I'. 0200 - Diesel Generator pre-operational checks and inspections begun ;
- 2. 0230 - Diesel Generator started; operating parameters recorded
- 3. 0300 - Diesel Generator declared inoperable; shift electricians and duty foreman notified
- 4. 0330 - Begin hanging tags and prepering for troubleshoot:ng activities. Technical Specification ACTION statements performed.
Subsequent troubleshooting efforts at the local control panel by electricians revealed a faulty relay. The faulty relay, K2, prevented the flashing of the generator exciter field. A new relay was obtained from stores and inspected to ensure proper working order and intended use. Following inspection, it was brougnt the local control panel for installation at 0715. For work continuity and efficiency, it was da:1ded et 0700 to have backshift personnel complete the job and then go home. The following events occurred at the indicated times:
- 1. 0430 - Electricians begin troubleshooting at the Diesel Generator local control panel. Faulty relay identified and removed.
- 2. 0600 - Electricians proceed to stores to obtain new relay; relay inspected
- 3. 0715 - New relay brought to local control panel for installation.
SIMULATOR CONTROLLER Should the Simulator Control Room page repair personnel to confirm estimated repair completion time, report that the work is proceeding smoothly and the diesel should be returned to service around 0900 this mornino The relay is installed by 0830 and tags are lifted at 0850. SIMUL ATOR CONTROLLER At 0850, call the simulator Unit Shift Supervisor and report that the Diesel Generator is reacN for restart. Simulator Control Room operators will start the diesel generator and allow it to run until such time es Technical Specification requirements are satisfied. All readings and parameters are normal. Page 8.1 -2
.j 4
. WORK REQUEST ~ ~
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- Rev 0 7/22/6?
MINI-SCENARIO 8.1.3 l 1 METPAC COMPUTER FAILURES PRE-EXERCISE CONDITIONS Resources and Facilities Department personnel periodically perform operability checks on f various emergency response equipment. During a routine check of EOF equipment on September l 26,1989, one of the two METPAC computers located in the Dose Assessment Area was found to I be inoperable. A failed color graphics card was suspected. The computer was removed that afternoon en0 brought to the Information Resources Group at Seabrook Station for repair. No work has been performed yet. Repairs are expected to be completed during the efternoon of the-27th and the computer is expected to be returned to the EOF on the 28th. EXERCISE FAILURE INFORMATION Upon EOF activation, the METPAC Operator will report to the EOF Dose Assessment Area. The ' assigned dose assessment controller should inform him that one METPAC computer is not in the room. Taped to the desk space where the computer would normally be is a piece of paper with the following message: "Out for repairs. Back on 9/28/89 " l When he attempts to start the remaining METPAC computer, intercede and Inform him that he has started the computer, however, the following error messages appear: File allocation table bad, drive c Non-System disk or disk error All subsequent efforts to " boot" the computer are unsuccessful. METPAC COMPUTER AT THE STATE OF NEW HAMPSHIRE EOC At 1045, the assigned State of New Hampshire player controller will inform the EOF Coordinator that the METPAC Computer in the State EOC is not functioning properly. The i computer " boots" up correctly and the message "METPAC files found" appears. At that point, the i program ceases to run. Subsequent investigations will find a failed 8287 math co-processing card. METPAC COMPUTER AT THE YNSD ESC The Yankee Nuclear Services Division Engineering Support Center (ESC) is not participating in this exercise. As requested by the EOF, the controller simulating the ESC should state that the ESC METPAC computer is not available. Page 8.1-3
Rev 0 7/22/69 MINI-SCENARIO 8.1.4 DIESEL GENERATOR B AIR COMPRESSOR FAILURE AND STARTING AIR RECEIVER DAMAGE All aspects of this Mini-Scenario prior to OSC activation will be simulated by oesignated controller personnel. OSC player personnel may respond as directed by the TSC. The assigned controller (s) should refer to the attached room sketch while implementing this Mini-Scenario. While operating to supply air to its two (2) associated Starting Air Receivers, Starting Air Compressor 2B catastrophically fails. A cylinoer head impacts the inlet line of Starting Air Receiver TK-45C causing a weld failure between the line and the tank. The concurrent failure the TK-45D inlet backflow Check Valve,1-DG-V-69B, allows both Starting Air Receivers to vent to the B Diesel Generator Room. Appropriate alarms are received in the Control Room at 0805. Auxiliary Operators (simulated by the Simulator Controller) will be dispeiched to investigate. SIMUL ATOR CONTROLLER 5 minutes after Dispatch request, call the simulator Unit Shift Supervisor and report that: e Air Compressor 2B is destroyed and compressor parts are scattered around air receiver skid.
- No other equipment appears to be mmaged.
- Local control panel low starting air pressure alarms are in.
- A loud hissing is emanating from the TK-45C inlet line; e small weld crack is visible.
- TK-45C end TK-45D air pressures are 200 and 270 psia resoectivelv: both are decreasina 1
The Short Term Emergency Director or Site Emergency Director may direct maintenance personnel to replace the damaged compressor and faulty check valve, and repair the broken inlet line. If these actions are taken, the assigned controller (s) should utilize the following information: 4 NOTE: All actions in the room prior to the Alert declaration were performed by simulated Auxiliary Operators and consisted of damage inspection and assessment. No repairs have been started yet. Any OSC personnel entering the room after the Alert declaration will be seeing it for the first time.
- 1. The compressor motor appears to be undamaged. Test runs confirm this assessment.
- 2. As part needs are identified to the inventory Department, state that the requested parts are in stock.
- 3. Allow all work to progress, however, the compressor and receivers will not be returned to service until after the end of the exercise.
1 l l Pege 8.1 -4 1
- y 0
. ATTACHMENT TO HINI-SCENARIO 8.1.4 7/22,69 B DIESEL GENERATOR BUILDING and STARTING AIR SKID Door !
1 PLAN VIEW Mtr L cal Control l I I l GROUND EL IControi Center Panet i
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* +A The following local annunciators are in alarm: ;
Starting Air STARTING AIR PRESSURE LOW l Receiver TK-45D STARTING AIR PRESSURE LOW LOW Check Valve 1 -DG-V- 69B (Failed Open) V VIEW A- A Isolation Valve 1-DG-V-68B (0 pen) Starting Air j Receiver TK-45C lsolation valve i Check Valve / N[ m i MN 7 DG-V-71B (0 pen) i l 1-DG-V-70Bf [M1 AIR @
-- Filter l
,................. ....' j e
- 1-DG-F-140B l
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' COUPLING BELT Starting Air * .
l ' Compressor 2B l Motor l HOUSING
I Rev i j 9/19/89 I MINI-SCENARIO 8.1.5 f SSNS. MEDIA CENTER AND JTIC SIMULATION INSTRUCTIONS Tills MIN!-SCENAllio ilAS BEEN DELETED l ! l l 4 i f Page 8.1 -5
Rev 1 9/19/89 l' This page' intentionally left blank due to the deletion of Mint-Scenario 8.1.5. l 1 I i i 1 i I 1 Page 8.1-6
Rev 0 7/22/S9 MINI-SCENARIO 8.1.6 ' CONTROL CELL INSTRUCTIONS FOR EXTERNAL ERO INTERFACE SIMULATIONS'
- l. ' General Instructions and Comments A. The' following information should be used as a basis for simulating
~
n . responses B. Controllers may add to, delete.from or otherwise modify any of the following mformation in respons6 to player actions as deemed appropriate. C. Controllers should thoroughly acquaint themselves with any referenced documents -
. and forms prior to the exercise.
- 11. American Nuclear insurers-A. Start Time: As initiated by players B. ERO
Contact:
Health and Safety Coordinator C. Contact Location: EOF D. Topic (s) Discussed:
- 1. Initiating events
- 2. Current situation and accMent prognosis
- 3. Status of actual or potential radiological releases
- 4. Protective actions recommended and/or implemented
- 5. Known offsite damages or injuries
- 6. Establishment of exclusion or restricted areas E. Information to Provide:
1; At 1200: ANI team will be dispatched to EOF Estimated arrival time: 1700 on 9/27/89
' Team members:
1 Site Engineer 1 Health Physicist 5 Claims Processing Personnel
.1 Lawyer Request directions to EOF and need for passes Request work stations and availability of clerical support ANI has made lodging provisions for its team til. American Nuclear Society A. Start Time: As initiated by players I B. ERO
Contact:
Industry Liaison C. Contact Location: EOF D. Topic (s) Discussed:
- 1. General accident status
- 2. Transmittal of approved news releases E. Information to Provide:
- 1. Telecopy number for press releases Page 8.1-7
l Rev 0 7/22/30 ' l , 1 IV. Institute of Nuclear Power Operations i A. Start Time: As initteted by players ! B. ERO
Contact:
Industry Liaison
. C. Conteet Location: EOF. -j D. Topic (s) Discussed:
1
- 1. General eccident information and response status l 2. EOF switchboard number ]j 3 EOF DCC telecopy number
- 4. Resources eveilable through INP0 Emergency Resources Manuel
- 5. DO NOT orovide any response outdance or recommendations )
E. Information to Provide: j
- 1. Telecopy number Y. NRC Emergency Notification System l
While the Unusual Event and Alert declarations are in effect, request that NHY call back every 30 minutes with an update until the event is terminated. After declaretton of a Site Aree Emergency, request that the ENS line be continually menned. A. Start Time: As initiated by players B. ERO
Contact:
Emergency Operations Manager C. Contact Location: TSC D. Topic (s) Discussed:
- 1. Information contained on Form ER 2.0D
- 2. Any other questions related to the accident or associated response actions
- 3. DO NOT orovide any cuidance. racammendations or directions E. Information to Provide:
- 1. 10 minutes after the declaration of a Site Area Emergency, inform your contact that the NRC wants the HPN line established by NHY Provide the exercise HPN number to the contact.
- 2. 5 minutes efter declaration of e Site Area Emergency: Inittel Activetion Team will be dispatched to E0F Estimated arrival time @ EOF: 1400 on 9/27/89 Team members:
Site Team Leader Reactor Safety Coordinator Safeguerc's/ Security Coordinator Emergency Responce Coordinator Public Affairs Coordinator
'i Government Lielson Coordinator Protective Measures Coordinator Health Physics Coordinator Team will fly to Pease AFB Air Force ground transportation to the EOF and Media Center has been errenged. The Public Affairs Coordinator will be proceeding directly to the ,
Media Center. !
- 2. If esked, en Expanded Activation Team will not be dispatched unless a General Emergency is declered i i
Page 8.1 -8
- Rev 0 7/22/89 VI. NRC Health Physics Network A. Start fime: As initiated by players; should be approximately 1130 if the contact has not been initiated by 1145, establish the HPN and identify yourself es the NRC HPN Communicator.
B. ERO
Contact:
Health and Safety Coordinator C. Contact Location: EOF' D. Topic (s) Discussed: -
- l. Information contained on HPN Forms
- 2. Any other questions related to radiological aspects of the accident or associated response actions
- 3. DO NOT orovide any cuidance. recommendations or directions E. . information to Provide:
- 1. .Telecopy number for HPN forms Yll. PSNH Control Center A. Start Time: As initiated by players B. ERO
Contact:
Corporate Support Manager C. Contact Location: EOF D. Topic (s) Discussed:
- 1. Information contained on Form ER 3.30
- 2. If requesteo, indicete that the power grid is stable anc that power supplies are adequate
- 3. DO NOT orovide any outdance. recommendations or directions Ylli. Westinghouse A. Start Time: As initiated by players B. ERO
Contact:
Industry Liaison C. Contact Location: EOF D. Topic (s) Discussed:
- 1. Availability of Westinghouse resources Accident and transient analysis Fuel damage assessment Replacement fuel and parts to support recovery operations
- 2. DO NOT orovide any response auldance or recommendations '
E. Information to Provide:
- 1. 5 minutes after requested by EOF: A team will be dispatched to EOF i
Estimated arrival time @ EOF: 4 hours after request i Team composition as requested by players Team will fly to Logan Request assistance with ground transportation and lodging errengements Rental cars Directions to EOF and required passes Page 8.1-9 1
f Rev 0 7/22/59 J IX. YNSD Engineering Support Center - A. Start Time: As initiated by players B. ERO
Contact:
Industry Liaison C. Contact Location: EOF D. Topic (s) Discussed:
- 1. Availability of Yankee Mutual Assistance Plan (YMAP) resources Contrciler should obtain a copy from the SSREP for use during exercise. .
If they are listed in the YMAP, state that requested resources are available.
. R:imate arrival time based on:
Timo to prepare resource for travel Travel time to EOF from resource home site
- 2. DO NOT orovide any auldane remmendations or directions of a technical or enaineerina nature
- 3. If requested, inform the EOF that the ESC METPAC computer is not available.
X. YNSD TLD Van Coordinator A. Start Time: As initiated by pla,ers B. ERO
Contact:
Dosimetry Records Personnel C. Contact Location: EOF D. Topic (s) Discussed:
- 1. Provide edditional TLDs a
l Page 8.1 - 10 1
l Rev 1 9/6/89 MINI-SCENARIO 8,1.7 NRC RESPONSE AT EOF The following information should be utilized as a basis for simulating the NRC response. The controller may expand on any of the following information as deemed appropriate. DISPATCH and TRANSPORTATION TO EOF NRC Region I dispatched an initial Activation Team to the EOF at 1130. The team consisted of: Site Team Leaoer Public Affairs Coordinator Reactor Safety Coordinator Government Liaison Coordinator Safeguaros/ Security Coordinator Protective Measures Coordinator l Emergency Response Coordinator The team flies to Pease Air Force Base (AFB) and receives military ground transportation to the EOF and, in the case of the Public Affairs Coordinator, the Media Center. Personnel arrive at the EOF and Media Center at 1400. LODGING AND TRANSPORTATION ARRANGEMENTS NRC made their own lodging arrangements with Pease AFB. They have also made provisions for ground transportation. BRIEFINGS AT THE EOF Upon arrival, NRC personnel will need a oriefing(s) concerning:
- 1. What caused the accident?
- 2. What is the current situation and accident prognosis?
- 3. Have there been or are there currently any releases from the plant?
- 4. What is the potential for further releases and when might they be terminated?
- 5. What Drotective Action Recommendations has NHY issued?
- 6. What Protective Actions have been implemented?
Team members will also want to review ENS and HPN forms, and emergency response documentation. The Licensing Coordinator should designate ERO members to interface with NRC Team personnel. WORK STATIONS I All personnel will need work stations in or near the EOF except for the Public Affairs Coordinator who has requested a work station at the Media Center. He will need a oedicated phone. The Reactor Safety Coordir.stor will request establishment of the TELTREND Communications Pactege. ADDITIONAL RESPONSE If asked, an Expanoed Activation Team will not be dispatched unless a General Emergency is declared MINI-SCENARIO 8.1.2 DIESEL GENERATOR A LOCAL CONTROL PANEL Page 8.1 - 1 1
( i I i NEW HAMPSHIRE YANKEE l SEABROOK STATION 1989 GRADED EXERCISE 8.2 NHY ORO MINf-SCENARIOS f
l k h l F l j NNY OFFSITE RESPONSE ORGANIZATION
, Mini-Scenario 8.2.1 l
L General' Instructions and Comments A. NHY Offsite Response Organization (ORO) personnel in this
*~
- "onsite" exercise are participating in the role of {
' player / controllers. Media Center and JTIC representation will not be available.
B. In this role their actions will not be evaluated. C. The actions (for exercise purposes) of ORO participants are depicted on the attached flow diagram. For exercise purposes it is assumed that the NHY ORO is operating in Mode' 2 (full). D. The actions indicated on the attached flow diagram represent the minimum actions needed to sustain exercise play. E. Precautionary and protective action decisions of towns in the Commonwealth of Massachusetts have been predetermined for exercise purposes. ORO drill participants should review the pre-scripted news releases and EBS messages contained in this mini-scenario to familiarize themselves with the-message content. The approximate time when the messages should be issued are indicated on the ORO News Release /EBS Message Key. ORO participants-are expected to coordinate timing of PAR decisions with New Hampshire exercise-participants. F. Participants are expected to fill in the blank spaces on the pre-scripted news releases and EBS messages. Examples of the information to be added to these messages ares
- 1. the number of the news release /EBS message;
- 2. the specific times emergency classification levels are declared by onsite players;
- 3. the time the messages were released; and
- 4. the approval signatures on the messages.
- 5. changes.may be made if actual meteorological conditions warrant content changes.
8.2-1 JJG8709 l
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NEWS RELEASES /EBS MESSAGES APPROX. TIME DESCRIPTION CATEGORY 1000-1045 ORO Activation News Release I 1100-1145 Mode 2 " SITE AREA EMERGENCY" - News Release ! No Release; No Protective Actions 1100-1145-- " SITE AREA EMERGENCY" EBS 1200-1300 Precautionary Actions for Farmers EBS and Farm Workers i 8.2-2 JJG8709
! e: 4 %/l 2 T_ NEWS RELEASE 1 Massachusetts Offsite Response Organization of New Hampshire Yankee THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL Release ORO ACTIVATION Page 1 of 2 NEWINGTON, N.H. - / /. - At a.m., New Hampshire Yankee's Offsite Response Organization (NHY ORO) was activated following the declaration of an Alert at the Seabrook Station Nuclear Power Plant operated by New Hampshire Yankee. There have not been releases of radioactive material from the plant. According to New Hampshire Yankee, an Alert is the second lowest of four emergency classifications that apply to nuclear power plants. The Alert declaration represents a substantial reduction in plant safety. According to Peter J. Stroup, Offsite Response Director, the NHY ORO was activated as a precautionary measure due to the current plant emergency. NHY ORO staff members are reporting to the Emergency Operations Center in Newington, N.H., and other emergency facilities in Massachusetts. The NHY ORO has been in contact with Massachusetts state and local officials. , To address rumors and questions, toll-free numbers have been established for Massachusetts residents. These should be used to check questionable information about the emergency. To receive information, Massachusetts residents can call 1-800-111-2222. For recorded information on station conditions oniv, residents can' call 1-603-111-2111. For recorded information concerning Massachusetts, residents can call 1-617-111-2112. For recorded information concerning New Hampshire, residents can call 1-603-111-2113. 8.2-3 JJG8709 l I
I M , 8:Atg C NEWS RELEASE j i Massachuset:5 Offsite Resoonse Organization of New Hamosnire Yankee THIS IS A DRIIJ, *** THIS IS A DRILL *** THIS IS A DRILL . l Page 2 of 2 Members of the media with questions on the New Hampshire Yankee (NHY) ORO can call 1-800-111-2223. Members of the media are urged to come to the Media Center in Newington, N.H. THIS IS A DRILL
- Approved: Date/ Time:
Approved: Date/ Time: Approved: Date/ Time: i l l 8.2_4 JJG8709 l
I n , s: E C NEWS RELEASE I.// l Massachuset:s Offsite Response Organization of New Hampshire Yankee MODE 2'--SITE AREA EMERGENCY - NO RELEASE; NO PROTECTIVE ACTIONS THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL l Page 1 of 2
~
Release NEWINGTON, N.H. -- / / -- At , New Hampshire l Yankee Offsite Response Organization (NHY ORO) was informed that ! a Site Area Emergency had been declared at the Seabrook Station Nuclear Power Plant operated by New Hampshire Yankee. The Site
. Area Emergency was declared at .
There have not been releases of radioactivity from the plant. A Site Area Emergency is the second highest emergency classification that applies to nuclear power plants. This emergency classification involves actual or likely major failure of plant functions needed for the protection of the public. According to Peter J. Stroup, NHY Offsite Response Director, NHY ORO emergency personnel have reported to the NHY Offsite Response Emergency Operations Center in Newington, N.H., and other emergency facilities in Massachusetts. The NHY ORO has been in contact with Massachusetts state and local officials. The NHY ORO is operating under Mode.2. Under this mode, Massachusetts has not responded to the emergency with their own ! response plan. The Governor of Massachusetts has delegated ! emergency authority to the NHY ORO. The NHY ORO will implement l its entire plan, or, if requested, only parts of the plan. Emergency authority was delegated to the NHY ORO at . , For the latest information, Massachusetts residents should j listen to their local Emergency Broadcast System radio stations: WLYT-FM (92.5) and WHAV-AM (1490). To address rumors and questions, a toll-free number has been established for the public. The number is 1-800-111-2112. 1 i I l 8.2-5 JJG8709 ! 1
@02%C NEWS RELEASE v
Massachusetts Offsite Response Organization of New Harnpshire Yankee THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL
. Page 2 of 2 Members of the media with questions on the NHY ORO can call 1-603-111-2223. Members of the media are urged to come to the Media Center in Newington, N.H.
THIS IS A DRILL
- Approved: Date/ Time:
Approved: Date/ Time: Approved: Date/ Time: 8.2-6 JJG8709
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p '75 - e Mv :esi CEBS MESSAGE Massachusetts Offsite Response Organization of New Hampshire Yankee ' THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL Page 1 of 2 SITE AREA EMERGENCY Date Message Released Time Message Released' Released by: Peter J. Stroup NHY Offsite Response Director "A SITE AREA EMERGENCY has been declared at Seabrook Nuclear Power Station. A SITE AREA EMERGENCY means that some significant releases of radioactive materials could occur, although any releases are not expected to go beyond levels set by the United States Environmental Protection Agency, except near the Seabrook Station site boundary. The New Hampshire Yankee Offsite Response Organization has been 1 notified and is responding to the problem. The New Hampshire Yankee Offsite Response Director is reviewing site conditions at this time and is discussing the situation with Massachusetts government officials. ; The Governor of Massachusetts recommends the following: The United States Coast Guard has been requested to enforce a five mile safety zone in the ocean waters near Seabrook Station. All offshore boaters near the plant are advised to relocate in waters farther than five miles from the plant or return to their local marinas. Boaters should not re-enter the five-mile zone until further notice. In addition, emergency information brochures are mailed annually to residents of the communities of Salisbury, Amesbury, Merrimac, Newbury, West Newbury, and Newburvoort. If you are in any of these communities, you should look up that emergency information. If these are unavailable, information can be found in area telephone books. this information could be helpful in understanding future messages. THIS IS A DRILL 8.2-7 JJG8709 1
M 4 ep W9C EBS MESSAGE Massachusetts Offsite Response Organization of New Hor..pshire Yankee THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL Page 2 of 2
~
If you know of any neighbors or co-workers with hearing or l language problems, please inform them of this message." {
"Once again: A SITE AREA EMERGENCY has been declared at Seabrook Nuclear Power Station.
This message will be repeated frequently on this station until new information is available. Stay tuned to this EBS station for the latest official information. If you are in any of the New Hampshire eastern Rockingham County communities, you should tune to a local radio station in New Hampshire for news about your community. Actions recommended in this message are intended only for persons in communities within ten miles of Seabrook Station."
- THIS IS A DRILL
- I i
8.2-8 JJG8709
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. i EBS MESSAGE !
Massachusetts Offsite Response Organization of New Hampshire Yankee I THIS IS A DRILL *** *** THIS IS A DRILL THIS IS A DRILL PRECAUTIONARY ACTIONS FOR FARMERS AND FARM WORKERS Date Message Released Time Message Released Released by: Peter J. Stroup NHY Offsite Response Director The following message from the Governor of Massachusetts is directed to farmers and food distributors in the communities of Salisbury and Amesbury. l Due to the emergency condition which has been declared at Seabrook Station, State authorities have recommended that precautionary actions be taken by farmers in some areas surrounding the plant. These actions are called preventive protective actions and are based on policy adopted long before Seabrook Station was operational. They do not mean a release of radiation has occurred or will occur. i According to State officials, farmers and dairy operators in the communities of Salisbury, and Amesbury should: i Move all milk-producing livestock inside a barn or other shelter. Provide the animals with stored feed and water and reduce sources of outside air into their buildings. Move outside feed supplies indoors or cover them, if possible. Store back-up supplies of water inside buildings and j cover outdoor wells, rain barrels, tanks or other sources of collected water.
- Call 555-1111 for more information.
l
*THIS IS A DRILL
- l 8.2-9 JJG8709
.)*
t 1 i. NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 8.3 STATE OF NEW HAMPSHIRE MINI-SCENARIOS i f l { l m _ __ _ ___ _. !
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, STATE OF NEW HAMPSHIRE 1
Mini-Scenario 8.3.1 General Instructions and Comments A.- LState of New Hampshire personnel in this "onsite" exercise ' are participating in the role of player / controllers. Media ' Center and JTIC' representation will not be available. B. In this role-their actions will not be evaluated. ' l
- C. .The actions (for drill purposes) of.New Hampshire exercise participants are depicted on the attached flow diagram.
D. The actions 1 indicated on.the attached flow diagram represent the minimum actions needed to sustain exercise play. E. Precautionary'and. protective action decisions of the State of New Hampshire have-been predetermined for exercise purposes., New Hampshire exercise participants should review the pre-scripted' news' advisory and EBS' messages contained in this mini-scenario to familiarize themselves with the message content. The' approximate time when the messages should be issued'are indicated on the News Advisory /EBS Message. Key. New Hampshire participants are expected to coordinate timing of PAR decisions with ORO drill participants. F. Participants are expected to fill in the blank spaces on the pre-scripted news advisories and EBS messages. Examples of the information to be added to these messages are:
- 1. the number of the news advisory /EBS message;
- 2. the specific times emergency classification levels are declared by onsite players; l
- 3. the time the messages were released; and l
1
- 4. the approval signatures on the messages.
- 5. changes may be made if actual meteorological conditions j warrant content changes.
I 1 8.3-1 JJG8686
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r Rev 0 7/22/89 NEW HAMPSHIRE NEWS ADVISORY /EBS MESSAGE KEY APPROX. TIME DESCRIPTION CATEGORY 0915-0945 Alert " declared at Seabrook News Advisory Station
~
1100-1145 Site Area Emergency EBS 1130-120d NH Governor' declares State of News Advisory Emergency for Seacoast
<1200-1230 Precautionary Actions for schools EBS 1200-1300 Instructions for Farmers .Ners Advisory l
l i 8.3-2 JJG8686 l
( NO. DATE/ TIME APPROVED THIS IS A DRILL .*** THIS IS A DRILL *** THIS IS A DRILL Page 1 of 3 FOR IMMEDIATE RELEASE ALERT DECLARED AT SEABROOK STATION CONCORD, N.H. - Governor Judd Gregg has activated the New Hampshire office of Emergency Management's emergency response organization today following the declaration of an " Alert" condition at New Hampshire Yankee's Seabrook Station, in Seabrook, New Hampshire. The Alert was declared at . I There has been no release of radioactivity from the plant. ! An Alert is the second lowest of four emergency-classification levels which apply to nuclear power facilities, and represents a reduction in plant safety. An Alert presents no danger to public health and safety. The Governor said the State Office of Emergency Management has activated the Emergency Operations Center in Concord, New Hampshire, which will be fully operational shortly. In addition, the Governor said the Office of Emergency Management is establishing communications with local emergency response organizations in the.17 seacoast area communities around the plant known as the Emergency Planning Zone (EPZ). These communities are: Seabrook, Hampton, Hampton Falls, Kensington, North Hampton, South Hampton, Brentwood, Exeter, Kingston, East Kingston, Rye, Portsmouth, New Castle, Newfields, Greenland, Newton and Stratham. health and safety at this time. The Governor stressed that there is no danger to public l t THIS IS A DRILL *** 8.3-3 JJGB686
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@ Tho NEflS Ncw Hampshir00ffice ADVISORY of EmcrgenepM l
i l THIS IS A DRILL. *** THIS IS A DRILL *** THIS IS A DRILL Page 2 of 3 ALERT DECLARED AT SEABROOK STATION (continued) George Iverson, Director of the New Hampshire Office of Emergency Management, issued the following statement: "At this time, we have activated the New Hampshire Office of Emergency Management's Emergency Response Plan and the substantial resources that support this plan. I would like to emphasize that there is no cause for concern for local residents living in the vicinity of the plant. materials into the environment.There has been no release of radioactive We have activated some of our resources because our chief concern is to assist the public in taking are the correct protective actions if and when these actions necessary, This is what we have trained and retrained to do
... prepared ourselves to assist the public during such times."
For the latest information, New Hampshire residents in the Emergency Planning Zone (EPZ) should listen to their local news broadcasts. their emergency Residents of the information EPZ are also advised to review calendars. find additional emergency information Visitors at public to the area will recreational facilities. A toll-free telephone number has been established for New Hampshire residents to receive information on the emergency situation and check questionable information. That number is 1-800-111-2222. In addition, telephone lines have been established for those interested in obtaining recorded information concerning the emergency at Seabrook Station and actions being taken by public safety officials in New Hampshire and Massachusetts. For recorded information on station cond?tions only, 1-603-111-2111. call I For recorded information concerning New Hampshire, 1-603-111-2112. call For recorded information concerning Massachusetts, call 1-603-111-2113. i THIS IS A DRILL *** j 8.3-4 JJG8686 l I
&' Tho NEWS Ncw Hampshirooffica ADVISORY of EmcrgCncy l
THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL l Page 3 of 3 l ALERT DECLARED AT SEABROOK STATION (continued) Members of the news media with questions on the New Hampshire Office of Emergency Management's response to the emergency should call 1-800-111-2223. Members of the media are also urged N.H. to come to the Media Center located in the Newington, Town Hall. j Approved: Date/ Time: NHOEM Response Director Approved: Date/ Time: NHOEM Media Liaison Approved: Date/ Time: NHOEM Spokesperson END OF NEWS ADVISORY
*** THIS IS A DRILL ***
i I i i l 8.3-5 JJG8686 l w__--______-__-___-_______ - - j
.Q Tho NE/IS ADVISORY of Emcrgen NcdHampshiroOffica THIS IS A DRILL ***
THIS IS A DRILL *** THIS IS A DRILL SITE AREA EMERGENCY DATE RELEASED: . TIME RELEASED: RELEASED BY:
"A SITE AREA EMERGENCY has been declared at Seabrook Station.A SITE AREA EMERGENCY means that some release of radioactive materials could occur, although any releases are not expected to go beyond levels set by the United States Environmental boundary. Agency, except near the Seabrook Station site Protection New Hampshire Emergency Management and public health officials are reviewing the emergency conditions at Seabrook Station.
State and local Emergency Operations Centers are functioning, and State and actions. necessary local emergency workers are prepared to take any Residents of Brentwood, East Kinaston, Exeter, Greenland, Hamoton, Hamoton Falls, Kensincton, Kinoston, New Castle, Newfields, Newton, North Hampton, Portsmouth. Rye, Seabrook, South Hampton information and Stratham should look up their emergency brochures. information also have been provided at hotels, motels, Posters, signs and businesses, park offices and beach facilities in these towns. This information could be helpful in understanding future messages. If you know of any neighbors or co-workers with hearin language problems, please inform them of this message.g or Once again: Station. A SITE AREA EMERGENCY has been declared at Seabrook This message will be repeated frequently on this station until new information is available. the latest official information. Stay tuned to this EBS station for If you are in northeastern Massachusetts, you should tune to a local radio station in Massachusetts for news about your town. . l Actions recommended in this message are intended only for persons in communities within *** ten miles of Seabrook Station." THIS IS A DRILL *** ' 8.3-6 JJG8686 i
O Tho Ncw HampshiroofficD 6f Emcrg:ney 7 l NEWS ADYISORY I L ! NO. DATE/ TIME APPROVED THIS IS A DRILL .
*** THIS IS A DRILL ***
THIS IS A DRILL , Page 1 of 3 FOR IMMEDIATE RELEASE NH GOVERNOR DECLARES STATE OF EMERGENCY FOR SEACOAST CONCORD, N.H. - Governor Judd Gregg has issued an Executive Order declaring a State of Emergency for towns and cities in southeastern Rockingham County. The announcement was made at
, and was necessary because of emergency conditions at Seabrook Station. According to New Hampshire Yankee, operators of the Seabrook Station, SITE AREA EMERGENCY was declared at Seabrook Station at .
i A SITE AREA EMERGENCY is the third highest of four emergency classifications that apply to nuclear power plants. This emergency classification involves actual or likely major failure of plant functions needed for the protection of the public. The 17 Seacoast area communities around the plant, an area known as the Emergency Planning Zone (EPZ), are affected by tho State of Emergency order. These communities are: Seabrook, Hampton, Hampton Falls, Kensington, North Hampton, South Hampton, Brentwood, Exeter, Kingston, East Kingston, Rye, Portsmouth, New Castle, Newfields, Greenland, Newton and Stratham. The Governor said the order will extend until the emergency i conditions at Seabrook Station have ended. Before issuing the order, Gregg consulted with State Office of Emergency Management and public safety officials, who concurred with his course of action. Governor Gregg also coordinated the order with New Hampshire Yankee and State of Massachusetts officials. The New Hampshire Governor said he took this step in order to put the full resources of the state at the disposal of emergency management officials at state and local levels.
*** THIS IS A DRILL ***
8.3-7 JJG8686 l l
& :Tho NEMSNcw Hampshirooffice ADVISORY of Emcrgency THIS IS A DRILL *** THIS IS A DRILL ***
THIS IS A DRILL Page 2 of 3
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NH GOVERNOR DECLARES STATE OF EMERGENCY FOR SEACOAST (continued) The United States Coast Guard has been requested to prohibit boating in the ocean waters within five miles of Seabrook i Station. All offshore boaters near the plant are advised to l relocate in waters farther than five miles from the plant or i return to their local marinas. Boaters should not re-enter the five-mile zone until further notice. Residents and visitors in the Emergency Planning Zone (EPZ) should listen to local Emergency Broadcast System radio stations for the latest information on the incident at Seabrook Station. The Emergency Broadcast System radio stations that cover the Emergency Planning Zone are: WOKQ-FM (97.5), WQMI-FM (95.3), WHEB-FM (100.3), WERZ-FM (107.1), WHEB-AM (750), WWNH-AM (1110), WTSN-AM (1290), WOMI-AM (1380), and WMYF-AM (1540). Residents of the EPZ are also advised to review their emergency information calendars. Visitors to the area will find additional emergency information at public recreational facilities. A toll-free telephone number has been established for New Hampshire residents to obtain information on the emergency situation and check questionable information. That number is 1-800-111-2222. In addition, telephone lines have'been established for those interested in obtaining recorded information concerning the emergency at Seabrook Station and actions being taken by public safety officials in New Hampshire and Massachusetts. j i For recorded information on station conditions only, call l 1-603-111-2111. For recorded information concerning New Hampshire, call 1-603-111-2112. For recorded information concerning Massachusetts, call 1-603-111-2113.
*** THIS IS A DRILL ***
8.3-8 JJG8686
Tho New Hampshirooffica of Emcrgency Menagement ' O9 NEMS ADVISORY I i THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL Page 3 of 3 l NH GOVERNOR DECLARES STATE OF EMERGENCY FOR SEACOAST (continued) i l Members of the news media with questions on the New Hampshire Office of Emergency Management's response to the emergency should call 1-800-111-2223. Members of the media are also urged to come to the Media Center located in the Newington, N.H. Town Hall. I Approved: Date/ Time: NHOEM Response Director Approved: Date/ Time: NHOEM Media Liaison Approved: Date/ Time: NHOEM Spokesperson END OF NEWS ADVISORY
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8.3-9 JJG8686 1 l L______--__-_-_________ l
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- NEWS . Tho New'HcmpshiroOffica ADVISORY of Emcrgen L,
THIS IS'A' DRILL -
*** THIS IS A DRILL *** THIS IS A DRILL.
Page 1 of 2 PRECAUTIONARY ACTIONS FOR SCHOOLS DATE RELEASED: TIME RELEASED: RELEASED BY: The following message from the New Hampshire Office of l Emergency Management contains information.about precautionary actions for schools in the Emergency Planning Zone for Seabrook Station. These actions apply only to schools and not to members y of the general public.
"As a precaution, the following public, private and
[ parochial schools in Hampton, Seabrook and Hampton Falls have been closed and students are being transported to Reception Centers. TOWN SCHOOL Seabrook Seabrook Elementary Hampton Falls Lincoln Akerman Elementary Hampton Winnacunnet High Hampton Sacred Heart Elementary Hampton Marston Elementary Hampton Hampton Christian Hampton Center Elementary Hampton Academy Junior High The Reception Center for schools in Seabrook is located at j Salem High School on Geremonty Drive in Salem. The Reception { Center for schools located in Hampton and Hampton Falls is Dover ]< High School on Durham Road in Dover. The early closing of schools in Hampton, Seabrook and Hampton Falls and relocation of students is a precautionary 3 measure based on policy adopted long before Seabrook Station was j operational. It does not mean that a release of radiation has ' occurred or w_i.JJ. i occur. Parents are urged not to attempt to pick up their children at school, since' children are already in the process of being taken to Reception Centers."
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8.3-10 JJG8686 i _m________. _ . _ _ _ . . - . _ -
Tha Ncw HampshiroofficD of Emcrg::ney Management ' 9 . NEWS ADVISORY ) 1 1 THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL
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Page 2 of 2 PRECAUTIONARY ACTIONS FOR SCHOOLS i (continued) , Day Care Center Administrators in Hampton, Seabrook, and Hampton Falls are being advised to notify parents or guardians to pick up their children early. This message will be repeated regularly until new information is available. Please stay tuned to this station for any further information or instructions.
*** THIS IS A DRILL ***
l l l l i 1 I 8.3-11 JJG8686 l
4 1 i l t NO. DATE/ TIME APPROVED ) d THIS IS A DRILL . **
- THIS IS A DRILL *** THIS IS A DRILL Page 1 of 2 FOR IMMEDIATE RELEASE INSTRUCTIONS GIVEN BY STATE FOR FARMERS AFFECTED BY SEABROOK STATION EMERGENCY i
' CONCORD, N.H. -- The New Hampshire Department of Public Health Services and the Department of Agriculture are monitoring the emergency conditions at the Seabrook Station in Seabrook, New Hampshire. The following actions are recommended for farmers and i farm workers in the communities of Seabrook, Hampton Falls,
! Hampton, Kensinaton, South Hampton, and North Hampton. All livestock and poultry should be moved inside a barn or other shelter. The animals should be placed on stored feed and well water and provided with reduced but adequate ventilation. Outside feed supplies should be moved indoors. If supplies cannot be moved indoors, they should be covered. Back-up supplies of water should be stored inside buildings. Outdoor wells, rainbarrels, tanks and'other sources of collected water should be covered, if possible. Farmers, farm workers, food processors and food distributors should check their emergency information brochures. If these are unavailable, questions may be answered by calling 1-603-862-2103 or 1-603-679-5616.
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8.3-12 JJG8686 {
Tho Now HampshiroOffica of Emcrgcncy Menngemqnt O.9 NEWS ADVISORY 1 THIS IS A DRILL *** THIS IS A DRILL *** THIS IS A DRILL j Page 2 of 2 INSTRUCTIONS GIVEN BY STATE FOR FARMERS'AFFECTED BY ! SEABROOK STATION EMERGENCY (continued) Approved: Date/ Time: NHOEM Response Director I. Approved: Date/ Ties: NHOEM Media Liaison Approved: , Date/ Time: NHOEM Spokesperson END OF NEWS ADVI3ORY
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8.3-13 JJG8686
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l NEW HAMPSHIRE YANKEE SEABROOK STATION i
. 1989 GRADED EXERCISE 9.0 PL ANT PARAMETERS
l l 1989 Gradu Exercise ' i i Elapseo Excore NIS Reactor Coolant Sys flow (TO RC5 Temperatures j Time Dower IQ ames 50 ces tooo A L000 8 t 000 C t000 D incere' Tavo Th
- A* Th *8* Th "C" Tn "D" 0 100 SE-4 ----- 100 100 t00 t00 633 589 618 618 6tB 618 30 .100- SE-4 ----- 100 100 100 100 633 589 618 618 618 618 l 60 100 5E ----- 100 100 100 '100 633 589 618 618 618 618 70 97 5 E-4 ----- 100 100 100 '100 632 588 617 617 617 617 80 94 4 E-4 ----- 100 100 100; 100 629' 587 616 616 616 616 90 91 4 E-4 ----- 100' .100 100 100 626 586 614 614
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614 614 ] 100 88 3 E-4 ----- 100 100- 100 IOO 624 585 612 612 612 612 110 84_ 2 E-4 ----- 100 100 100 100 621- 584 610 610 610 610 ,1 120 80. 2 E-4 ----- 100- 100 100 100 618 582 607 607 607 607 130 77 1 E-4 ----- 100 100 100' 100 617 581 606 606 606 606 140 74 9 E-4 ----- 100 100- 100 100 615 580 604 604 604 604 150 71 9 E-5 ----- 100 100 300 100 612 579 602 602 602 602 160 68 9 E-5 ----- 100 100 100 100 610 578 600 600 600 600 170 64' 8 E-5 ----- 100 100 100 100 607 577 597 597 597 597 180 60 7 E-5 ----- 100 100 100 100 603 576 595 595 595 595 190 0 SE-6 ----- 0 0 0 0 588 561 576 576 576 576 200 0 2E-9_ 0 0 O O 585 559 574 574 574 574 210 0 ?E-li 10116 0 0 0 0 575 551 566 566 566 566 220 0 (IE-11 138 0 0 0 0' 570 543 558 558 558 558 230 0 (IE-Il 135 0 0 0 0 562 534 549 549 549 549 240 0 (IE-ti 120 0 0 0 0 555 526 541 541 541 541 1 250 0 <tE-41 118 0- 0 0 0 545 518 533 533 533 533 260 0 (IE-11 118 0 0 0 0 533 509 $24 524 524 524 270 0 stE-Il 118 0 0 0 0 525 500 515 515 515 515 280 0 <tE-11 118 0 0 0 0 520 492 507 507 507 507 a 290- 0 (IE-61 118 0 0 t00 0 510 484 499 499 499 499 300 0 (IE-11 118 0 0 100 0 501 476 491 491 491 491 310 0 (IE-11 118 0 0 100 0 490 468 483 483 483 483 320 0 <1E-11 118 0 0 100 0 485 459 474 474 474 474 330 0 (IE-Il 118 0 0 100 0 475 451 466 466 466 466 340 0 (1E-11 118 0 0 100 0 468 442 457 457 457 457 350 0 <!E-11 118 0 0 100 0 460 434 449 449 449 449 360 0 <1E-11 lie 0 0- 100 0 450 426 441 441 441 '441 ' 370 0 clE-ll 118 0 0 100 0 445 418 433 433 433 433 380 0 (IE-Il 118 0 0- 100 0 435 409 424 424 424 424 390 0 <tE-11 118 0 0 100 0 422 400 415 415 415 415 400 0 (1E-11 118 0 0 100 0 415 392 407 407 407 407 4l0 0 (IE-l1 i18 0 0 100 0 408 384 399 399 399 399 420 0 (IE-11 118 0 0 100 0 397 376 391 391 391 391 430 0 <1E-11 IIB 0 0 100 0 393 373 388 388 388 388 440 0 <!E-11 118 0 0 100 0 385 359 374 374 374 374 450 0 <tF-11 118 0 0 100 0 372 -351 366 366 366 366 Rev 0 7/22/89 Page1
1 ! ! t t 989 Grad 20 Eucrcigo i a,, . Elapseo RCS Temperatures RC5 press PZR PRT PRT press RC5 HU/CD RCS *F : Time te T Te 8- Te *C Te 0" WR DSIG t vt t t vt K DstG m *r/Hr Subcoolmo .I O SSB 558- 550 558 -2235 62 c5 2 0 28 30' 558 558 558 558 2235 62 65 2 0 24 60 558 558 558 558 2235 62 65 2 0 21 70 558 SSB 550 558 2235 61 65 2 -7 22.
- 80. 558 558 558 558 2235 60 65 ,2 -7 26 90 558 558 558 558 2235 59 65 2 -7 29 100 558 558 558 .558 2235 58 65 2 -7 30 110 558 558 558 558 2235 56 65 2 -7 34 120 558 558 558 558 2235 55- 65 2 -7 36 130 558 558 558 558 ~2235 53 65 2 -7 38
-140 558 558 558 558 2235 52 65 2 -7 40 150 558 558 558 558 2235 51 65 2 -7 43 160 558 558 558 558 2235 50 65 2 -7 45 170 558 558 558 558 2235 48 65 2 -7 48 180 558 558 558 558 2235 46 65 2 -7 52 190 546 546 546 546 1270 0. 65 2 -50 -9 200 544 544 544 544 1132 0 65- 2 -50 -7 210 536 536 536 536 1173 0 65 2 -50 -3 220 528 528 528 528 1165 0 65 2 -50 9-230 .519 519 519 519 1160. 0 65 2 -50 18 240 511 511 511- 511 .1155 0 65 2 -50 25 250 502 502 502 502 1150 0 65 2 -50 34 260 494 494 494 494 1140 0 65 2 -50 37 270 486 486 486 486 750 0 05 2 -50 46 280 478 478 478 478 1125 30 85 20 -50 1 290 469 469 469 '469 t120 40 85 20 -50 62 300 460 460 460 460 1015 50 85 20 -50 75 310 452 452 452 452 860 40 85 20 -50 70 320 444 444 444 444 735 30 85 20 -50 60 330 436 436 436 436 740 20 85 20 -50 50 340 428 428 428 428 740 25 85 20 -50 42 350 419 419 419 419 740 30 85 20 -50 50 360 410 410 410 '410 740 35 85 20 -50 60 370 402 402 402 402 800 40 85 20 -50 70 380 394 394 394 394 800 40 85 20 -50 83 390 386 386 386 386 800 40 85 20 -50 95 400 378 378 378 378 800 40 85 20 -50 100 4to 369 369 369 369 800 40 85 20 -50 110 420 360 360 360 360 800 40 85 20 -50 117 430 352 352 352 352 800 40 85 20 -50 125 440 344 344 344 344 800 40 85 20 -50 135 450 ??5 ?36 336 336 B00 40 P5 70 -50 120 l
Rev 0 7/22/89 I
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i, 1089 Gradoo Euerciso t . Elapseo Rx vessen Level 2 . AMA - -. 5 CCP 58 CSS ECC5 Accumulator Pressures Accan Cntmnt Time Statte Ovnamte Flow m GDM Dress T T C- 'D- t vueal) press O- ------ 100 0 0 0 .0 625 625 625- 625 6400 0. a 30 ------ 100 0 0 0 0 625- 625 625 625 6400 0 60 ------ 100' f O O O O 625 625 625 625 6400 0 70 ------ 100 0 0 0 0 625 625 625 625 6400 0 J 1 80 ------ 100 0 0 0 0 625 625 625 625 6400 90 ------ 100 0 ) 0 0 0 0 625. 625 625 625 6400 0 100 .------ 100 0 0- 0 0 625 625 625 625 6400 0 l10 ------ 100 0 0 0 0 625 625. 625 625 6400 0 120 ------ 100 0 0 0 0 625 625 625 625' 6400 0 130 ------' 100 0 0 -O' .0 625 625- 625' 625 6400 0 140 '------ 100 0 0 0 0- 625 625 L625 625 6400 0 l 150 ------ 100 0 0 0 0 625 625 625- 625 6400 0 160 ------ 100 .0 0 -0 0- 625 625 625 625 6400 0 170 ------ 100 0 0 0 0 625 625 625 625 6400 0 180 ------ 100 0 0 0, 0 625 625 625 625 6400 0 190 100 ------ 0 450 550 0 625 625 625 625 6400 0 1-200 100 ------ 0 450 550 0 625 625- 625 625 6400 02 r 210 100 ------ 0 450 550 0 625 625 625 625 6400 04 220 100 ------ 0 450 550 0 625 625 625 625 6400 05 230 100 ------ 0 450 550 0 625 625 625 625 6400 07 240 100 ------
- 0. 450 550. 0 625 625 625 625 6400 08 250 100 ------ 0 450 550 0 t25 625 625 625 6400 09 260 100 ------ 0 450 550 0 625 625 625 625 6400 1 270 100 ------ 0- 450 550 0 625 625 625 625 6400 11 280 100 ------
0 500 700 0 625 625 625 625 6400 290 12 100- ------ 'O 450 550 0. 625 625 625 625 6400-300 ------ 13-40 0 475 225 0 625 625 625 625 6400 t4 310 ------ 40 0 500 300 0 625 625 625 625 6400 14 320 ------ 40 0 500 300 0 625. 625 625 625 6400 15 330 ------ 40 0 500 300 0 625 625 625 625 6400 16 340 ------ 40 0 500 300 0 625 625 625 625 6400 16 350 ------ 40 0 500 300 0 625 625'.625 -625 6400 17 360 ------ 40 0 500 300 0- 625 625 625 .625 6400 18 370 ------ 40 0 500 300 0 625 625 625 625 6400 19 380 ------ 40 0 500 300 0 625 625 625 625 6400 2 390 ------ 40 0 500 300 0 625 625 625 525 6400 21 400 ------ 40 0 500 300 .0 625 625 625 625 6400 22 410 .------ 40 0 500 300 0 625 625 625 625 6400 23 420 ------ ' 40 0 500 300 0 625 625 625 625 6400 23 430 ------ 40 0- 500 300 0 625 625 625 625 6400 23 440 ------ 40 0 500 300 0- 625 625 625 625 6400 23 450 .------ en 0 250 300 0 625 625 625 625 6400 23 Rev 0 7/22/89 Page 3 _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - . _-- -~ - -
y5 1939 Cradec Exeretse ElacSec RwSTLevel Cntmnt Rectre Stern Generator t evels in DERCENT Time tet810allons SUme Sumo A"NA 'B' ND ' C' NA "D NA . " A" WA ~ B' WA C" WA 'O' WA 0 480,000 0% 0' 50 50 50 50 66 66 86- 66 30 480,000- 0 %. O' 50 50 50 50 86
-86 86 86-60 480,000 0%' 0' 50 50 50 50 86 86 86 66 70 ~ 480,000 10% 0' 50- 50 50 50 86 86 86 86 80 480.000 25%' 0' 50 50: .50 50 86- 86 86 86 90 480.000 40% 0' 50 50 50 50 86 86 86 86 100 480,000 55% 0' 50 50 50 50 86 '86 E6 86-110 480,000 70% 0 50 50 50 50 86 66 86- 86 120 480,000 35%- O' 50 50 50 50 86 86 86 86 130 480.000 100% 0'. 50 '50 50 50 86- 86 86 86 140 480,000 100% 0' 50 50 50 50 86 86 86 86 ISO 480,000 100% 0* 50 50 50 50 86 86 86 86 160 480,000 100% 0' 50 50 50 50 86- 86 86 86' 170 480,000 100% 0' 50 50 50 50 86 86 86 86 180 480,000 100% 0' 50 50 50- 50 86 86 86 86 190 470,000 100% 0' O O O O 70 70 70 70 200 460,00'0. 100% . 0' O O O O 81 81 81 81 210 450,000 100% 0* 30 30 30 30- 88 88 88 88 220 440,000 100% 0' 45 45 45 45 91 91 91 91 230 430.000 100% 0' 50 50 50 50 93 93 93 93 240 420,000 100% 0' 50 50 50 50 95 95 95- 95 250 410,000 100% 0' 50 50 50 50 95 95 95 95 260 400,000 100% 0'- 50 50 50 50 95 95 95 95 270 '390,000 100% 0' 50 50 50 50 95 95 95 95-280 378,000 100% 0' 50 50 50 50 95 95 95 95 290 368,000 100% 0 50 50 50 50 95 95 95 95 300 361.000 100% 0' 50 50 50 50 95 95 95 95 310 353,000 100% 0' 50 50 50 50 95 95 95 95' 320 345,000 100% 0' 50 50 50 50 95 95 95 95 330 337,000 100% 0' 50 50 50 50 95 95 95 95 340 329,000 100% 0' 50- 50 50 50 95 95 95 95 350 321.000 100% 0' 50 50 50 50 95 95 95 95 360 313,000 100% 0' 50 50 50 50 95 95 95 95 370 305,000 100% 1' 50 50 50 50 95 95 95 95 380 297,000 100% 3' 50 50 50 50 95 95 95 95 390 289,000 100% 4' 50 50 50 50 95 95 95 95 400 281,000 100% 5' 50 50 50 50 95 95 95 95 410 273,000 100% 6' 50 50 50 50 95 95 95 95 420 265,000- 100% 7' 50 50 50 50 95 95 95 95 430 257,000 100% 8' 50 50 50 50 95 95 95 95' 440 249,000 100% 9' 50 50 50 50 95 95 95 95
_4,50 744 500 100% 1 0' 50 50 50 50 05 05 05 c5 Rev 0 7/22/89
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4 1989 Gracea Exorcise Elapseo . 5/G Pressure in P516 Total EFW Letcown Charging RCS Leakage Core Thermal Time A- 9- C* 0- Flow GDM - Flew GDM Flow GDM (GDM) Dewer Mwt 0 962 962 962 962 0 77 89 0 3418 f' 30 962- 962 962 962 0 77 89. 0 34:1 60 962 962 962 962 0 77 89 0 3411 70 965 965 965 965 0 50 150 80 3309 ! 80 969 969 969 969 0 50 150 80 3207 90 974 974 974 974 0 50 150 80 3105 100 978 978 978 978 0 50 150 80 3003 110 984 93 4 984 984 0 50 150 80 2867 120 990 990 990 990 0 50 150 80 2731 130 995 995 995 995 0 50 150 80 2629 l' 140 999 999 999 999 0 50 150 80 2527 150 1004 1004 1004 1004 0 50 150 80 2425 160 1000 1008 1008 1008 0 50 150 80 2323 170 1014 1014 1014 1014 0 50 150 80 2187 180 1020 1020 1020 1020 0 50 150 80 2051 190 1069 1069 1069 1069 1600 0 0 1000 55 i 200 1028 1028 1028 1028 1600 0 0 1000 53 l 210 915 915 915 915 800 0 0 1000 El 220 855 855 855 855 500 0 0 1000 50 230 795 795 795 795 250 0 0 1000 48 240 740 740 740 740 200 0 0 1000 46 250 690 690 690 690 200 0 0 1000 44 260 635 635 635 635 200 0 0 1000 44 270 587 587 587 587 200 0 0 1000 44 280 545 545 545 545 200 0 0 1000 44 290 500 500 500 500 200 0 0 1000 44 i 300 450 450 450 450 200 0 0 1000 44 I 310 406 406 406 406 200 0 0 1000 44 320 380 300 380 380 200 0 0 800 44 330 350 350 350 350 200 0 0 800 44 340 320 320 320 320 200 0 0 800 44 350 295 295 295 295 200 0 0 800 44 360 270 270 270 270 200 0 0 800 44 I 370 250 250 250 250 200 0 0 800 44 380 225 225 225 225 200 0 0 800 44 390 205 205 205 205 200 0 0 800 44 400 186 186 186 186 200 0 0 800 44 410 155 155 155 155 200 0 0 800 44 420 140 140 140 140 200 0 0 800 44 430 125 125 125 125 200 0 0 800 44 440 110 110 110 110 200 0 0 800 44 450 800 t00 100 100 200 0 0 B00 44 Rev 0 7/22/89 i i l Page5 l l
1989 Grsded Extreise j Ela05ec 13 8 kV 13 8 kV 416kV 416kV 416 kV Diesei Gen 416 kV Diesei Den Tima Bus I volts Bus 2 V9ts Bus 3 VNt'- Bus a volts But E5 Volt? I A kw Rus E6 Velt? 18kW 0 14015 14024 4402 4388 4400 0 4410 0 30 14015 14024 4402 4388 4400 0 4410 0 60 14015 14024 '4402 4388 4400 6083 4410 0 70 14015 14024 4402 4388 4400 for 4410 0 t 80 14015 14024 4402 4388 4400 cu~ation 4410 0 ! 90 14015 14024 4402 4388 4400 of test 4410 0 l 100 14015 14024 4402 4388 4400 run; then 4410 0 110 14015 14024' 4402. 4388 4400 to '0" 4410 0 120 14015 14024 4402 4388 4400 0 4410 0 l
- 130 14015 14024 4402 4388 4400 0 4410 0 140 14015 14024 4402 4388 4400 0 4410 0 150 14015 14024 4402 4388 4400 0 4410 0 160 14015 14024 4402 4388 4400 0 4410 0 170 14015 14024 4402 4388 4400 0 4410 0 180 14015 14024 4402 4388 4400 0 4410 0 190 14015 14024 4402 4388 4400 0 4410 0 200 14015 14024 4402 4388 4400 0 4410 0 210 14015 14024 4402 4388 4400 0 4480 0 220 140t5 14024 4402 4388 4400 0 4410 0 230 14015 14024 4402 4388 4400 0 4410 0 240 14015 14024 4402 4388 4400 0 4410 0 250 14015 14024 4402 4388 4400 0 4410 0 260 14015 14024 4402 4388 4400 0 4410 0 270 14015 14024 4402 4388 4400 0 4410 0 280 14015 14024 4402 4388 4400 0 4410 0 290 14015 14024 4402 4388 4400 0 4410 0 300 14015 14024 4402 4388 4400 0 4410 0 310 14015 14024 4402 4388 4400 0 4410 0 320 14015 14024 4402 4388 4400 0 4410 0 330 14015 14024 4402 4388 4400 0 4410 0 340 14015 14024 4402 4388 4400 0 4410 0 350 14015 14024 4402 4388 4400 0 4410 0 360 :4015 14024 4402 4388 4400 0 4410 0 370 14015 14024 4402 4388 4400 0 4410 0 300 14015 14024 4402 4388 4400 0 4410 0 390 14015 14024 4402 4388 4400 0 4410 0 400 14015 14024 4402 4388 4400 0- 4410 0 410 14015 14024 4402 4388 4400 0 4410 0 420 14015 14024 4402 4388 4400 0 4410 0 430 14015 14024 4402 4388 4400 0 4410 3 440 14015 14024 4402 4388 4400 0 4410 0 450 '4n15 14024 4402 4TAs 44no o 4410 6 Rev t 9/7/89 l
Daoe 6 _________-__-_a
w - 1
. t 989 Gradoo Exorciso' Etapseo Critt:al Sa'ety
. Function - Status Time Subertticality Core Coolino Hast Sink RCS inteerttv Contamment inventoav RHR Flow Radiation Men 0 GREEN GREEN GREEN GREEN GREEN . GREEN GREEN GREEN
'30 GREEN . GREEN GREEN GREEN GREEN ' GREEN GREEN.
' GREEN 60 LGREEN' GREEN GREEN GREEN GREEN ' GREEN- . GREEN GREEN 70 GREEN- GREEN GREEN GREEN GREEN GREEN ' GREEN GREEN 80 GREEN. GREEN GREEN GREEN GREEN GREEN GREEN GREEN 90 GREiN GREEN' GREEN GREEN GREEN GREEN. GREEN- GREEN 100 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN I10 ' GREEN , GREEN GREEN GREEN GREEN GREEN GREEN' GREEN ,
120 GREEN ' GREEN GREEN GREEN GREEN GREEN GREEN' GREEN 130 ' GREEN- GREEN GREEN GREEN GREEN GREEN GREEN GREEN 140 GREEtt GREEN GREEN GREEN GREEN GREEN' GREEN GREEN 150 GREEN GREEN - GREEN GREEN GREEN GREEN GREEN GREEN 160 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN 170 GREEN GREEN GREEN . GREEN GREEN GREEN GREEN GREEN 880 GREEN GREEN . GREEN GREEN GREEN GREEN GREEN GREEN 190 GREEN' YELLOW - YELLOW GREEN GREEN- YELLOW GREEN GREEN 200 GREEN ' YELLOW YELLOW GREEN GREEN YELLOW GREEN GREEN 210 GREEN' ' YEL LOW . GREEN GREEN GREEN YELLOW GREEN GREEN-220 GREEN. YELLOW . GREEN GREEN GREEN ELLOW GREEN GREEN 230 GREEN YELLOW GREEN GREEN GREEN YELLOW GREEN GREEN ,- 240 GREEN VELLOW GREEN GREEN GREEN YELLOW GREEN GREEN-l 250 GREEN YELLOW GREEN GREEN GREEN YELLOW GREEN GREEN 260 GREEN YELLOW GREEN ' GREEN GREEN (ELLOW GREEN GREEN 270 GREEN ' GREEN GREEN GREEN GREEN YELLOW GREEN GREEN 280 GREEN YELLOW GREEN GREEN GREEN GREEN . GREEN GREEN 290 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN 300 ' GREEN GREEN GREEN GREEN GREEN GREEN- GREEN GREEN 310 GREEN GREEN GREEN GREEN GREEN GREEN GREEN- GREEN 320 GREEN GREEN GREEN GREEN GREEN GREEN ' GREEN GREEN 330 GREEN- GREEN GREEN GREEN GREEN GREEN GREEN ' GREEN
. 340 GREEN ' GREEN GREEN GREEN GREEN GREEN GREEN' GREEN 350 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN 360 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN 370 GREEN GREEN GREEN GREEN GREEN GREEN 09EEN- GREEN 380 GREEN. GREEN GREEN GREEN GREEN GREEN GREEN- GREEN 390 GREEN- GREEN GREEN. GREEN GREEN GREEN GREEN GREEN 400 GREEN GREEN GREEN GREEN GREEN GREEN ' GREEN GREEN 410 GREEN- GREEN GREEN GREEN GREEN GREEN GREEN GREEN 420 GREEN GREEN GREEN GREEN GREEN GREEN GREEN- GREEN 430 GREEN GREEN -GREEN GREEN GREEN GREEN GREEN GREEN 440 GREEN GREEN GREEN GREEN GREEN GREEN GREEN GREEN 450 GAEEN GDEEN SAEEN GAEEN 'GAEEN GREEN GAEEN GAEEN Rev 0 i 7/22/89 Dage 7
[. _. _ _ _ - - - - - - _ _ - - _ - - - _ - . - - - - - _ - - - - - _
NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 10.0 RADIOLOGICAL DATA I
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1989 GRADED EXERCISE 10.1. iNPLANT DATA'
'10.1.1 PRE-EXERCISE RDMS TRENDS .
10.1.2 l INITI L SURVEY MAPS 10.1.3 RDMS DURING EXERCISE 10.1.4 SURVEY MAPS AND DOSE RATES DURING EXERCISE 10.1.5 CHEMISTRY SAMPLE DOSE RATES j' 10.1.6 '. HEALTH PHYSICS AIR SAMPLES ANALYSES 10.2 .' CHEMISTRY DATA-
, -10.2.1
- RCS DATA (CHEMICAL ANALYSES)
I 10.2.1'1 PRIMARY CHEMISTRY REPORT . 10.2.1.2 REACTOR COOLANT SYSTEM CHEMISTRY. DATA 10.2.2- GAMMA' SPECTROSCOPY ' ANALYSES 10.2.2.1 REACTOR COOLANT SYSTEM-10.2.2.2 CONTAINMENT ATMOSPHERE 10.2.2.3 WRGM AIR FILTERS 10.3 METEOROLOGICAL DATA 1-10.4.ONSITE OUT OF PLANT DATA i 10.5 0FFSITE DATA-l. 1 l L. - _ _ - _ _ _ _ _ _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - _ l
e. NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 10.1 INPL ANT DAT A 10.1.1 PRE-EXERCISE RDMS TRENDS i L _ _ - _ __ _ -- _ _ - . - - - - . i
/ - 4, L EANNUAL EXDC2SE, Revision 2.0 ! u
' Containment Containment Containment' Containment
,* 3106 AX107 L M105 . 'M104 POSTLOCA'AJ POST LOCA B ~ PERS. BATCH HI~ ~ PERS HATG LOW ALERT ~8.00E+00 8.00E+00 4.00E+03 1.00E+01-HIM 1.00E+01 1.00E+01 1.00E+04 1.00E+02
'3CHARIO TIXE; RihrL -sehr d/hr < mR/hr b
~
'20-Sep-69: 8.80E-01 : ;7.10E-01 '8.36E-01 8.36E-01
'.' 21-Sep-89, 8.80E-01.- '* 10E-01~ 8.36E-01 8.36E-01
.22-Sep-89 8.80E-01 ".10E-01 8.36E-01 8.36E-01
'23-Sep-89' 8.80E-01.' .10E-01 '8.36E-01 8.36E-01 24-Sep-89 8.80E ".10E-01 8.36E-01 '8.36E-01 25-Sep 8.80E 7.10E-01 8.36E-01 8.36E-01
'26-Sep-89' .8.80E .10E-01 8.36E-01 8.36E-01
'27-Sep-89 8.80E-01 ' ".10E-01 8.36E-01 8.36E-01 RER Vault' PR Vault PR Vault RHR Vault AN301 M303 ' M302 AN304 PURP A IDW - PUNP A HI PDMP B IDW PURP B HI
- ALERT 4.00E+01' 4.00E+01' '4.00E+01 4.00E+01 HIG 1.00E+02: 1.00E+02 1.00E+02' 1.00E+02 SCENARIO *::I . nR/hr 2R:hr dihr: niihr 20-Sep-si 1.80E+01. 1.80E-01 2.00Et01 2.00E,01 Sep-69 1.80E+01 - 1.30E+01 2.00E-01 2.00E+01 22-Sep 1.80E+01 1.80E+01 2.00E+01 .2.00E+01 23-Sep-89 1.80E+01 1.80E+01 2.00E+01 2.00E+01 24-Sep 1.80E+01' 1.80E+01 2.00E+01 2.00E+01 25-Seo-89 1.80E+01 1.80E+01 2.00E401 2.00E'01 26-Sep-89 1.80E+01' -1.80E+01 ' 2.00E+01 2.00E+01 l Sep-89 .'1.80E+01 1.80E+01 2.00E+01 2.00E'01 I
i PAB PAB PIB PAB .j AM205 AX233 AX234 AR204 23' S LOW 7' S LOW 7' S HI 7' N IDW ALERT 1.00E+00 2.00E+01 5.00E+01 2.00E+01 ' HIG 2.50E+00 1.00E+02 1.00E403 1.00E+02 SCENMIO TIME - mR/hr dthr tR/hr nRIhr 20-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 21-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 22-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 23-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 24-Sep-ai 1.50E-01 4.00E-00 4.00E+00 1.50E-01 25-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 M-Sep-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 27-Seo-89 1.50E-01 4.00E+00 4.00E+00 1.50E-01 9/20/89,Page10.1.1.1
s ANNUAL D:ERClSE. Revision 2.0 PAB PAB PAB PAB AX211 AX206 AM210 AX207 7' N HI -6' N LO -6' N HI CH PHP A ALERT 5.00E+01 2.00E+01 2.00E+01 1.00E+01 HIGH 1.00E+03 1.00E+02 1.00E+02 5.00E+01 SCENARIO T HI mR/hr d/hr 2/hr cRihr j 20-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E400 o 21-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E 00 22-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50Et00 M ep-89 1.50E-01 2.90E+00 3.50E+00 3.50E+00 24-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E+00 25-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E+00 26-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E+00 27-Sep-89 1.50E-01 2.90E+00 3.50E+00 3.50E+00 PAB PAB PAB PAB AM208 AM209 AX232 AM229 CH PHP B CH PMP 128 VCT SAKP RH ALERT 1.00E+01 2.00E+01 5.00E+03 5.00E+00 HICH 5.00E+01 5.00E+01 2.00E+04 1.00E+01 SCENARIO T 1I drhr dihr d br dthr 20-Sep-si 3.50E-00 . 50E-01 2.54Et03 1.50E-01 21-Sep-89 3.50E-00 1.50E+01 2.54E+03 1.50E-01 22-Sep-89 3.50E+00 1.50E+01 2.54E+03 1.50E-01 23-Sep-89 3.50E+00 1.50E+01 2.54E+03 1.50E-01 24-Sep-89 3.50E+00 1.50E+01 2.54E+03 1.50E-01 25-Sep-89 3.50E+00 1.50E*01 2.54E+03 1.50E-01 26-Sep-89 3.50E+00 2.50Et01 2.54Et03 1.50E-01 27-Sep-89 3.50E+00 1.50E-01 2.54E 03 1.50E-01 Admin. Bldg. ControlEcom Containment Containent AH703 AH501 AP111 NG101 MAINT SHOP CR AREA PARTICULATE GAS ALERT 1.00E+00 1.00E+00 . 00E-09 5.00E-04 HIGH 2.50E+00 2.50E+00 1.00E-07 5.00E-03 SCENARIO TIME mR/hr tR/hr uCi/cc uCile: 20-Sep-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 21-Sep-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 22-Sep-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 23-Sep-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 24-Sep-89 1.50E-01 1.50E-01 .30E-10 9.80E-06 25-Sep-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 26-Sep-89 . 50E-01 . 50E-01 .30E-10 .80E-06 l 27-Seo-89 1.50E-01 1.50E-01 9.30E-10 9.80E-06 9/20/89, Page 10.1.1.2 i
y, 1 y ' ANNUAL EIERCISE, Revision 2.0 Containment- PAB' > PAB WRGM
.j L_ , GA112. 01273: CA274 NG222'
.{
La ENCL EM 'EX - CONT ENCL HISC ' *.'ENT. IDW -
< ALERT- 5.00E+01c =5.00E+01 -5.00E+01 4.00E-06~ "
HIGH 1~00E+02' 1.00E+02 1.00E+02 1.00E SCENARI0'IIKE 'CPR CPM CPM _uCi/cc 20-Sep 2.50E+00 2.30E+01 3.10E+01 2.66E-06
*- 21-Sep-89' 2.50E+00 2.30E+01 3.10E+01 2.66E-06 22-Sep-89 2.50E+00 2.30E+01 3.10E+01 2.66E-06 o .-23-Sep-89 2.50E+00 2.30E+01 3.10E+01 2.66E-06 24-Sep-89 2.50E+00. 2.30E+01 3.10E+01 2.66E-06 25-Sep-89 2.50E+00 2.30E+01 3.10E+01 2.66E-06 26-Sep-89 2.50E+00 2.30E+01 3.10E+01 2.66E-06 27-Sep-89' 2.50E+00 2.30E+01 3.10E+01 .2.66E-06 WRGK WR2 WRGH Control'RoonAir
.NG223 .NG224 CC225 GA510 MID HI EITL TRAN-A EAST ALERT 1.00E-03 1.00E-01 1.13E+05 5.00E+01 HIGH 2.00E-03 2.00E-01 4.51E'05 .1.00E+02 SCENARIO T1HE uCi/cc uCi/c: uCi.se: - CPM 20-Sep- i. '1.00E-04 1.00E-02 2.05E-01 1.62E+01 21-Sep-89 1.00E-04 1.00E-02 2.05E 1.62E+01
;22-Sep-89 1.00E-04 1.00E-02 2.05E+01 1.62E+01 23-Sep-89 1.00E-04 1.00E-02 2.05E+01 1.62E+01 24-Sep-89 1.00E-04 1.00E-02 2.05E+01 1.62E+01 25-Sep-89 1.00E-04 1.00E-02 2.05E-01 1.62E+01 26-Sep-89 1.00E-04 1.00E-02 2.05E+01 1.62E+01 2*l-Sep-89 1.00E-04. 1.00E-02 2.05E-01 1.62E'01 ControlRoonAir ControlRoonAir- Control Roon Air' HainSteamLine GA511 GA520 GA521 GM801 TRAN A WEST TTAN B EAST TPM B WEST IDOP1 ALERT 5.00E+01 5.00E+01 5.00E'01 5.00E-01 HIGH 1.00E+02 1.00E+02 1.00Et02 5.00E+00
' SCENARIO IIME CPH CPM CPK mR/hr 20-Sep-89 1.92E+01 1.94E+01 1.61E+01 3.90E-01 21-Sep-89 1.92E+01 1.94E+01 1.61E+01 3.90E-01 22-Sep-69 1.92E+01 1.94E+01 1.61E+01 3.90E-01 23-Sep-89 1.92E+01 1.94E+01 1.61E+01 3.90E-01 24-Sep-89 1.92E+01 1.94E+01 1.61E-01 3.90E-01 25-Sep-89 1.92E+01 1.94E+01 1.61E-01 3.90E-01 26-Sep-89 1.92E+01 . 94E+01 1.61E-01 3.90E-01 27-Sep-89 1.92E+01 1.94E+01 1.61E-01 3.90E-01 f 1 9/20/89,Page10.1.1.3
= _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ - _ _ _ _ _ _ _ -
ANNUALEXERCISE, Revision 2.0 MainSteam'Line MainSteanLine MainSteamLine Reactor Coolant
.'GH803 GM804- GM802 LM240 l LOOP 2 LOOP 3 LOOP 4 LETDN LOW ALERT 5.00E-01 5.00E-01 5.00E-01 -1.39E+01 HIGH 5.00E+00- 5.00E+00 5.00E+00 5.56E+01 SCENARIO IIME mR/hr cR/hr mR/hr. ~u Ci/al 20-Sep-89 .3.90E-01 3.90E-01 3.90E '2.15E-03 21-Sep 3.90E-01 3.90E-01 3.90E-01 2.15E-03 22-Sep-89 3.90E-01 3.90E-01 3.90E-01 2.15E-03
'23-Sep-89 3.90E-01. 3.90E-01 3.90E-01 2,15E-03 L 24-Sep-89 3.90E-01 3.90E-01 3.90E-01 2.15E-03 25-Sep-89 3.90E-01 3.90E-01 3.90E-01 2.15E-03 26-Sep-89' 3.90E-01 3.90E-01 3.90E-01 2.15E-03 27-Sep-89 3.90E-01 '3.90E-01 3.90E-01 2.15E-03 Reactor Coolant Eeactor Coolant 67B kTB LM241 LK242 AH602 AH606 LETDN HI LEIDN AUTO TRDCK BAY COMPACTOR
-ALERT- 1.39E+01 1.39E+01 2.50E+00 2.50E+00 HIGH 5.56E+01 5.56E+01 1.00E+01 1.00E+01 l
SCENARIO TIME UCi/ml uCi/cl mR/hr mR/hr L 20-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 21-Sep-89 2.15E-03 2.15E-03~ 2.00E-01 3.00E-01 22-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 23-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 24-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 25-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01. 26-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 27-Sep-89 2.15E-03 2.15E-03 2.00E-01 3.00E-01 h7B iTB h7B h7B AP610 NG611 CG612 AH601 ! WPB PART. WPB GAS WPB ETELEENT GAS PROCESSING ALERT 1.00E-09 5.00E-06 0.00E+00 2.50E+00 l HIGH 2.25E-09 1.00E-05 0.00E+00 1.00E+01 SCENARIOIIME UCi/ml uCi/ml uC1/see nR/hr 20-Sep-89 1.01E-10 7.80E-07 5.90E+01 3.00E-01 21-Sep-89 1.01E-10 7.80E-07 5.90E+01 3.00E-01 22-Sep-89 1.01E-10 .80E-07 5.90E+01 3.00E-01 23-Sep-89 1.01E-10 7.80E-07 5.90E+01 3.00E-01 24-Sep-89 1.01E-10 7.80E-07 5.90E+01 3.00E-01 25-Sep-89 1.01E-10 ~.80E-07 5.90E+01 3.00E-01 26-Sep-89 1.01E-10 * .80E-07 5.90E+01 3.00E-01 27-Sep-89 1.01E-10 .80E-07 5.90Et01 3.00E-01 9/20/89, Page 10.1.1.4
- )
] l ANNUALEXERCfSE, Revision 2.0 i
{ WPB WPB- WPB CONDENSER - j i
'AM603-- ,
AM604' AM605 GM810 l CONTROL ROOM CONTROL PANEL EXTRUDER- COND AIR E'iAC ALERT '2.50E+00 2.50E+00 5.00E+01 6.00E+02 HIGH 1.00E+01'_ 1.00E+01 1.00E+02 1.00E+03
-SCENARIO TIME :mR/hr aR/hr mR/hr . CPM 20-Sep-89 2.00E-01 4.00E-01 -2.40E+01 2.20E+01 -
21-Sep-89 2.00E-01 - 4.00E-01 2.40E+01 2.20E+01 22-Sep-89 2.00E-01 4.00E-01 2.40E+01 2.20E*01 _23-Sep-89 2.00E-01 4.00E-01 2.40E+01 2.20E+01 Sep-89' 2.00E-01 4.00E-01 2.40E+01- '2.20E+01-25-Sep-89 2.00E-01 4.00E-01 2.40E+01 2.20E+01 26-Sep-89 2.00E-01 4.00E-01' 2.40E+01 2.20E+01 i 27-Sep-89 2.00E-01 4.00E-01 2.40E+01 2.20E+01 SG BLOWDWN SG BIDWDWN SG BE%'N SG BIDWDWN LM216 LM212 LM213 LH214 LOOP 1 IDOP 2 IDOP 3 IDOP 4 ALERT ;.00E-05 2.00E-05 2.00E-05 2.00E-05 HICH 1.00E-04 1.00E-04 1.00E-04 1.00E-04 SCENARIO TIME uCi/a1 uC1/ml uCiln1 uC1/c1 20-Sep-89 4.53E-08 4 53E-08 4.53E-08 4.53E-08 21-Sep-89 4.53E-08. 4.53E-08 4.53E-08 4.53E-08 22-Sep-89 4.53E-08 4.53E-08 4.53E-08 4.53E-08 23-Sep-89 4.53E-08 4.53E-08 4.53E-08 4.53E-08 24-Sep-89. 4.53E-08 4.53E-08 4.53E-08 4.53E 25-Sep-89 4.53E-08. 4.53E-08 4.53E-08 4.53E-08 26-Sep-89 4.53E-08 4.53E-08 4.53E-08 4.53E-08 27-Sep-89 4.53E-08 4.53E-08 4.53E-08 4.53E-06 PAB PAB AP270 NG271 PART GAS 1 ALERT 1.00E-09 5.00E-06 l HIGH 2.25E-09 1.00E-05 l SCENARIO TIME 20-Sep-89 8.00E-11 8.00E-07 21-Sep-89 8.00E-11 8.00E-07 22-Sep-89 8.00E-11 8.00E-07 23-Sep-89 8.00E-11 8.00E-07 24-Sep-89 8.00E-11 8.00E-07 25-Sep-89 8.00E-11 8.00E-07 26-Sep-89 8.00E-11 8.00E-07 27-Sep-89 8.00E-11 8.00E-07 9/20/89, Page 10.1.1.5
- __2______ _ - _ _ _ - - - - - _ _ _ _
i c NEW HAMPSHIRE YANKEE SEABROOK STATION
~
1989 GRADED EXERCISE 10.1 INPL ANT DAT A 10.1.2 INITI AL SURVEY MAPS l i
i RCA TUNNEL UNIT 1 O C AomI.iuttoinc b J ll k ll. ll ll
' ' " ~ ~ '
V/ TO . _ .. UNIT 2 ! u
. -(]PAB F. . _
!!!E i
B ll (( llll lIl C I t VPB llll G . TO t PERS. H ATCH g H D ll Ill E g TO RHR L_ i
)
RCA TUNNEL A l B i C l D l E iF i G l H ALL i ALL ALL i ALL Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr i mR/hr l mR/hr i mR/hr mR/hr j mR/hr mR/hr i mR/hr com i UCi/cc com I cpm } I 8:00 <1 l <1 l <1 l <1 <1 I <1 <1 1 <1 l <100 11.05E 10 , As Read I 13 All count rates are nelcpm. I All air samples assume a 20 cubic Avolume. i
)
10.2.1.1
' :PABl PLAN: fATLEL.l(-);26' -?0" & (-):34- 0 "' {
.]
s . 1 b~ - . [
... E E A L; . - -
l- ,
-.. M E~ .
E D
.@ I n t O 10
- %@ O 3
- 'A 5l l i I 1 a,
} 1- 6
.- C B _
v . '2 (
. .ui,, ,. ... ov. . . ,, ,
utstivty nact f s-se* tt. g. j mF m ,
~
1 PAB PLAN AT EL M 26'-0" & M 34'- 0" A l 8 I C l D l E I F ' ALL I A1 ALL l ALL Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr i mR/hr I mR/hr j mR/hr mR/hr l mR/hr com I uCi/cc com I com
<1- l- <1 l 2 l 2 2 1 2 <100 14.48E 10 As Read l 56
-8:00 Allcountrates are netcpm. ;
All air samples assume a 20 cubic A volume. e, 10.2.1.2
b j P AB. PLAN AT EL. 2' - 0" & (-)'6' - 0"
~ susu . . m N RE 6508(1) ,. 4 ,
<==
M ==t_ E ......... . ...... B j,; i r M
~
""'L.J -- E, O
a1 1 .D c. uu ~~ .. c,..... t O c
,, L rai
....-... 1...7u1
'""agt" , O .,-g I--
l -- l n . . .. , < l _s y g, , , n.. n .,i < . . IDI O ,, , ,,, a
...n.._ ,,..- ,
O C....=4C U ,_
, D 3
- u. ~.,
a...,. D u..~.,.
, D
-1 g P!PE TRENCH
~
PAB PLAN AT EL 2'- 0" & (-) 6' - 0" E F Al.i. l All ALL i ALL A l B l C l D l l Dose Rate Smear Airbome lodine Parl Time Dore Rate mR/hr i mR/hr cpm l uCi/cc com I com mR/hr i mR/hr i mR/hr 1 mR/hr 55 <100 l 5.23E-10 As Read i 66
<1 <1 l 2 l <1 10 I 8:00 l Allcountrates are nelcpm.
All air samples assume a 20 cubicftvolume. i
. g . h<
I5.'- f j { t in 0,3 - : l
PAB PLAN AT ele 7' - 0 " l s l
./ ,
/
N i
\
c a u u ,. ,. [- " d, h ll ll1 l l
, _ _ _ _ _ -g gy -
A q ; A /
. crn - - 1
== ,
==
B 7_ e
,rm n w e:a i
i L._ H _ d U !!Ic$
= u 0.-.. . . . , . . . o,c . .
5 0 g C W g i (T iseef.ref t f**0.ap 2 E. n ee r w ife I j (f D
" M
( 4. e ==. . ( M9 )( 4 e ' *** C ul _.J ,l y(sitemal(D gW18 (ett t a NlI l
~
D 0 D-+ i O u
, U 1
u .,,e.. g(tst e e f e. t i (**?*= df I I (( .e > r *t T f e
'E a - -
( a.e .e ll (MARCINC FVM,
""- {(t**JFM'f8 , g ,g E D D - +l i O i ;
j
--} u -
E D - ' T <..u,*-,.-, 0
. s ...,0 D a ,_ g a L (--->-
nn rv ....,<e. a p - yy a
, __r ._
J w f
/
Y I N RE 6543
, a RE 6563(O e l
PAB PLAN AT EL 7'- 0" A 8 l C l D I E I F ALL l ALL ' ALL l All. i Dose Rate Smear Airbome lodine Part Time Dose Rate mR/hr l mR/hr com l UCi/cc cpm I com mR/hr I mR/hr i mR/hr l mR/hr 8:00 <1 1 8 I 82 l <1 25 l 4 <100 13.85E-10 , As Read i 49 i . All count rates are nelcpm. All air samples assume a 20 cubic flvolume. 10.2.1.4 I L_________-____-____-___ -
PAB PLAN AT EL. 25' - 0" - v. s, Q D com.arat c. tmc ar j i cintt r a in ct tu - -
^ =EH lil illi 1 _
- - =:S
- RM-RE 6515o 'g y -
~
3A S .Ii '
.::: -- l~' ' i C
4 .=,
=
RM-RE 6516 c:3 U !.
= =:S g _ h. ' ~_: _ ~~~~ ._.. . -
A N O lR g @N Gh @- @ RE 6520 * - I am
'5" L
C D d D a D ' " " 'Hh. E D !
- o D n ]@ __ _ o g C
a 3@ @@ @@ ~ e 3 a , ci E 3*v g 2~ C $-
]AB VI t==
~ ~
! i
=
E
=
3%a5
]W
'I C'" -
c=E '
~
= e
~~1 i
. @aC .y,.A ,
5 RE 6537
=
=
t g aC.-
- C 5 I tien ercas ta
, , _ _u
_h l! Xit i samett sm k4 = . . = L: t_
.t -
_ r_ 1,, . . i I m
- ': lillllli l l l ]
) 00RIC,8ClO TE
~
l PAB PLAN AT EL 25'- 0" D E F I ALL i ALL ALL l A1 A l 8 i C l i l Smear Airbome lodine Part Dose Rate Date Rate Time com I com mR/hr i mR/hr i mR/hr l mR/hr ' mR/hr i mR/hr com I uCi/cc
<1 <100 (1.30E-10 l As Read i 16
<1 i <1 i <1 <1 l 8:00 <1 l L Allcount rates are nelcpm.
All air sample: as:ume a 20 cubic ft volume. i I 10.2.1.5
t .4 L-PAB PLAN AT EL.:53' - 0" J k g'."pT["";;;
, 3g"""; 3; 1 u '
..T.T. .".-2lp . . . .i . RM-RE 3 . :::6519
- = i
- 4 s ii E stuntra ceena ..
a o . RM-RE 6513 [ O l l 5l - 8C~
,O
~
--RM-RERM-RE 6511 6512 ' *O o E as-g RE 6567 e M-RE E 6568 6510 0
- c.n..,necriraa O
> e C g;;
H '> RE 6530 m -
.g y- i i eRM-RE 6529 l
,. =,
3 ""g'-' "'T"" PAB EX FAN j u
'~
- v i., *O 3 "
An
. c,;........a... 9,-) rx Cu;e- ;
]
i i ; m _. -- ..
...n i l
}
. = ! F -
i= y / j , ....s.,. . a j )
, y* i .
("" X. ,ql 3 2 i D E y, f9= 7 l - lar n=s Illi Il g g"E
' .c I l < F .
n
* . "r c:::
G . ...c .< >. . . n . n E
~
PAB PLAN AT EL 53'-0" A l B- l C l D l E i F 1 ALL-l A1 ALL i A1 Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr,l mR/hr i mR/hr i mR/hr mR/hr i mR/hr com i uCi/cc com I com 8:00 <1 i <1 i <1 i <1 3 i <1 <100 11.15E 10 As Read i 14 Allcount rates are nelcpm. AI! air sample: a::ume a 20 cubicftvolume. 10.2.1.6 a___--____-- . _ _ _ _ - _ - _ - - - _ _ _ - _ _ _ _
- P ABLPL'AN AT EL:. 81.' - 0" a:
EB
, N
-]
1Iii44IiI
. D s s e l . Q- g *-
w i immer i . I er i Ter r2 C'-
~
D ' a c B i s A, l l 1 1 PAB at EL 81'- 0" A l B l C l D 1 ALL Al.i. A1 All Time Dose Rate Smear Airbome lodine Part. mR/hr mR/hr mR/hr mR/hr com UCi/cc mm_, com 8:00 ' <1 <1 <1 <1 <100 2.11E 11 As Read As Read l Allcount rates are nelcpm. l All air samples assume a 20 cubic flvolume. 10.2.1.7 i
1: CONTROL BUILDING PLAN. AT EL. 75' - 0" ) t
- V i g,.as ! Z A l -2 = ,
Ab N g -
>+< <<+,s 7 q_ 4 3 g o _ j + 4 i u.u.a _ _
h 9 Y \l _ a -
- - ~
C O B 3 - 3 F 4N g - - 3 - D D 3
- \ -
b E Sh Z 7 E N 1 l CONTROL ELDG. at EL. 75' - 0" A l B l C l D E F E m m m 91ae Dose Rate Seear Airborne lodine Part. aR/tr tR/hr mR/hr mR/hr tR/hr aR/hr cpn uCi/cc cpa epa 8:00 (1 (1 <1 <1 (1 (1 (100 1.0E-10 As Read 13 All count rates are net eps. All air samples assume a 20 c d ic ft volume. 10.2.1.8
t TURBINE BUILDING PLAN AT EL. 21' - 0" j i i o g h M! C ') l ll r, y i F
'^
E
=
]
g n= y y CE il U
= *
, ~ 1U ,
~ ~
'"'J D C
. m rs
" g .. . . . . . g d, DPk:: OcE
= 7 rr
" / C. i I i i ! b 7 E E E C C)
- I in ) i C A ,2
' j 4 C 6 i i i 9 e ...!. c
.-i t
!_1
' d!
4
- 9 i i i .'t
... B
,_, t, i .i n > i c j
.c:::b k D cC]C g ,- g ,'j O#!
ma u : O
} UD
.... i. ]
g O j [;.
.... c d I.',_..O % ,_ ]
==
~
-"----"--};........_..
j , [5 C L_.............NONO......I E' J = :=., m" m1 1 - I- ,L hBB x.e -
;D 3 47o o % o (
].
TRBINE BLDG. at EL. 21' - 0" l- A l B l C l D E F AE An An Ag { Time Dose Rate Snear Airborne Iodine Part, i n/hr mR/hr mR/tr mR/hr mR/hr aR/hr est UCi/cc cra cps 1
- 00 il (1 <1 <1 <1 <1 (100 1.2E-10 As Read 15 All count rates are net eps.
Allairsasolesassitnea20cubicftvolume. L-_-___-__ . _ _ _ _ _ .
TURBINELBUILDING PLAN AT EL. 50'- 0" l il E
-a$ y l
D g
=== -
_P5L oi )
~
ni 3 . l' j Ly m, > ._ _. NN C - E ci 2 b l m CoMitMsit 64CATEks (I 3 ceMstns[R (- p) (, //
&ntattas {],
)
a qg - iI (B O CSM9tMi[R hattitts 9 O (B O
\.
. - _0
~~
h'/ g {, >1, - ; II I ll' ' ' E , rE a- lr-p.o. E ,, B c=== Q , o MatM
~ ~
= ~in~titm'stiI^ *N'tN.
. _ .ar------ m ets D .
T:
~ '
c A 8
; m T V
TutBINE BIDG. at EL. 50' - 0" A \ B \ C l D ALL E F ALL ALL ALL Time Dose Rate Smear Airborne Iodine Part. tR/hr mR/hr mR/hr al/hr 2/hr d/hr ces UC1/cc cpa CDE 8:00 <1 <1 <1 <1 (1 (1 (100 1.1E-10 is Read 14 l in. .1.in
l TURBINE PLANL AT EL. 7 5 ' - 0."
~
'"""""" l O .D E l h,.
0' ~ c-30
- Q ._
O g
-s f , ,
1 C O O m 0 t' "a - ',. '
~- N O (
[ "O 1 ' t O. c : - O b E'E . DI g , ,
- I l g .
I
. E$
I J "TE M A- p 1 y B 'A CONTROL BLDG. s . TURBINE BLDG at EL. 75' - 0" l C D E F ALL ALL ALL l ALL A l B \ Dose Rate Snear Airborne Iodine Part. Time tR/br aR/tr cpa uCi/cc cpa cpa . d/hr aR/hr aR/hr aR/hr (1 (1 <1 (100 1.3E-10 As Read 16 8:00 <1 (1 <1 , All count rater, are net cpa. ,
- f. Allairsaanlesassumea20cubicftvolume. f w___-____-_--- _ _ _ .
EAST FEEDWATER PlPE CHASE PLAN AT EL. 3' - 0"
., .~,
JJ
. e C
N e at sws:(t)
' B C at smsa(2) l '
R A h $
- OO -
EAST FEEDWATER PIPE CHASE PLAN AT EL 3'- 0" ~ A l B l C ALL 1 ALL ALL i ALL Time Dose Rate ~ Smear - Airbome lodine Part mR/hr. l mR/hr l mR/hr cpm uCi/cc cpm I cpm 8:00 <1 i <1 l <1 <100 l 4.81E-10 . As Read l 61 Allcount rates are net epm. All air :smple: at:ume a 20 cubic flvolume. 10.2.1.12 i l L__________ __ _ _ _ _ _ _ _ i
- u. 1 1
. EAST FEEDWATER PlPE CHASE I: PLAN AT EL. 21 ' - 0", 27' - 6 "
l l l
~
~
\
i N D 3
/ ....5 E]
, }Oy
/000
~
HYDROGEN ANALYSER , EAST FEEDWATER RPE CHASE AT EL 21' 0". 27'- 6" A l 8 l C l D l E I F ALL l ALL ALL i A1 Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr i mR/hr i mR/hr i mR/hr I mR/hr I mR/hr com i UCi/cc com i com N/A l N/A l <1 l <1 l <1 l <1 <100 14.81E-10 As Read i 61 lef Allcount rates are net epm. All air sarnples assume a 20 cubic ft volume.
's 10.2.1.13 l
. _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _____-________A
L .. WEST FEEDWATER PIPE CHASE PLAN AT EL: 3'- 0" i l l I I 1 j N
^
atswet(0 2 at swet (2) g N I I
- C I I WEST FEEDWATER PIPE CHASE PLAN AT EL 3'- 0" A l B l C ALL ALL ALL l ALL Smear Airbome lodine Part Time Dose Rate mR/hr i mR/hr i mR/hr com UCi/cc com l com 8:00 <1 l . <1 l <1 <100 13.01E 10 As Read j 38 Allcount rates are net cpm. .
All air samples assume a 20 cubic A volume. L 10.2.1.14
J MAIN STEAM FEEDWATER PLAN AT EL. 28'
/ /
C B ..
~
N X X' X X , X LX D D a
~
M ' f j 7 E,,j c=:= R1 I g 3D 0l0 . o oi
)
N F , , ,
$[ C
;4" El
', i;;"
b 7 .
]
~
MAIN STEAM FEEDWATERPLAN AT EL 28' ALL ALL l ALL A l 8 l C l D l E iF All l Part Date Rate Smear Airbome lodine Time Dose Rale com I cpm mR/hr i mR/hr i mR/hr l mR/hr mR/hr i mR/hr com l uG/cc I 61
<1 I <1 i <1 -l <1 l <1 l <100 l4.81E-10 l A: Read i 8:00 <1 i Allcountrates are netcpm.
All air samples assume a 20 cubicflvolume. 10.2.1.15 - ---- - - _ _______ _ _ _ _ _ _ _ _ ^ - - - - - - - - - - - - - - . _ _ _ _ _ , _ _
c s '
.,= tELECTRICAL TUNNEb(B) TRAIN L
PLANL AT EL. (--)'26' - 0" - V - o N-E U U
- g. I B
A n n- y C s
^
f" p El.ECTRICALTUNNEL (B) TRAIN PLAN AT EL (-) 26' - 0* A l B l C All. ALL ALL - l ALL Time Date Rate Smear Airbome lodine Part. mR/hr i mR/hr I mR/hr com uCl/cc com 1 - com 8:00 <1 I <1 l <1 <100 13.21E-10 As Read l 40
~
Allcount rates are nelcpm. All air samples assume a 20 cubic ft volume. 9 0 4 10.2.1.16
. ELECTRICAL TUNNEL (A) TRAIN PLAN AT EL. O' - 0" ;
L 1 A 1 c::-
- C -j
=_
B
\ %
e ELECTRICALTUNNEL (A) TRAIN PLAN AT EL O'- 0" - A l B l C ALL Au. ALL I ALL Time Dose Rate Smear Airbome lodine Part mR/hr i mR/hr i mR/hr com UCi/cc com I com B:00 <1 l <1 l <1 <100 11.2BE-10 As Read I 16 Allcount rates ere nelcpm. All air samples assume a 20 cubic flvolume. e 10.2.1.17
R.H.R. PLAN STAIRS . b A s 9 r
]L -
f N
- B it.
N
= -
mE c . , D - f E
=
MAN
'N b
, LIFT F h
- =
~M, ,
$ RM-6539
~
RHRVAULT STAIRWAY A l B i C l D l E i F ALL l ALL ALL i ALL Time Dose Rate Dose Rate Smear Airbome lodine Part
- mR/hr l mR/hr i mR/hr i mR/hr i mR/hr i mR!hr com i uCi/cc com ! com 8:00 6 l 9 l 15 1 27 l 33 I 37 <100 12.11E-10 . As Read i 27 Allcount rates are nelcom.
All air sample: a:sume a 20 cubic ftvolume. t 10.2.1.18
R.H.R., PL AN AT EL. O' - 1/2" & 3' - 2" l YAULT 1 I . E X @
? ]
b { _ I E F E A"M 6 C X , m k B CONT. SPR AY HXS. EL 3 ' - 2" l E D F _ MAN N U f LIFT "h 3
= = !
I
,,, meu
. M L m, ,
. O' - 1/2- VAULT 2 RM-6539 RHR VAULTS at EL O'- 1/2", & 3'- 2" ~
A l 8 l C l D l E l F ALL l ALL ALL i ALL Time Date Rate Dose RaLa Smear Airbome lodine ParL mR/hr l mR/hr l mR/hr l mR/hr l mR/hr i mR/hr com i uCi/cc com I com 8:00 9 l 20 l 25 l 34 1 36 1 33 <100 12.11E-10 As Read i 27 Allcount rates are nelcpm. A!! air samples assume a 20 cubic ft volume. t 10.2.1.19
R.H.R. PLAN AT EL. (-) 9' - 0", (-) 16' - 0" ) ; 4
.i VAULT 1 B E A f
s N CONT. SPR AY HX RHR HX
' \
i = MAN
'N E
I LIFT h
)
F E '~
= ,
5 D g
-' (-) i s - o- YAULT 2 (-) s - o-l RHR VAULTS ~at_EL M 9' 0", H 16'- 0" A l B l C l D I E l F A1 l A1 Al i A1 Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr i mR/hr I mR/hr mR/hr l mR/hr l mR/hr cpm I uCl/cc com ! com 8:00 8 j 19 l 25 24 1 27 l 29 <100 12.11E-10 ; As Read i 27 All count rates are nelepm.
All air samples assume a 20 cubic ft volume.
' * ^ ' ~^
R.Fj.R. PLAN AT EL. (-) 31'- 10" VAULT 1 C N M A %_ _ , N E MER CCNT. SPR AY HXS. RHR HX M Eiliiis E.
" F" D Eb
- MAN LFT
- =
- ':l=l
,N "h }
VAULT 2 1
~
RHR VAULTS at EL (-)310" A l B l C l D l E l F ALL l All. ALL l ALL Time Date Rate Dose Rate Smear Airbome lodine Part mR/hr i rnR/hr i mR/hr i mR/hr I mR/hr i mR/hr com l UCi/cc cpm i com l 8:00 8 l 19 l 25 1 23 l 53 1 29 <100 ( 2.11E-10 As Read l 27 Allcount rates are net cpm. All air samples assume a 20 cubic ft volume. M 10.2.1.21 q _ _ _ _ _ - _ ___ _ i
R.H.R. PLAN AT EL. (-) 50' - 0"
~
VAULT 1
. g
~
C
=
OM in ]
=
e s N A l l S AFETY INJEC PUMPS D E I __.
.. Der ,e -
man =
'm urr
.. - "h )-
r = [_ - V AULT 2 l . RHR VAULTS at EL ( 150'- 0" A l B l C { D l E l F ALL i AR \ ALL l ALL Dose Rate Dose Rate Smear Airbome i lodine Part Time mR/hr i mR/hr l mR/hr j mR/hr i mR/hr i mR/hr com I uCt/cc ! com I cpm 19 27 l 35 { 32 l 47 <100 12.11E-10 As Read i 27 8:00 9 l l Allcount rates are net cpm. 4 All air sangle: a:sume a 20 cubic ft volume. f 10.2.1.22 l
R.H.R. PLAN AT EL. (-) 61' - 0" VAULT 1 RM - RE 6538 5
- A - -
BO - llllll OO c e _ N CONT. SPRAY PUMPS RHR PUMPS . t g1 ; MAN l F , LIFT ,
~
OO ::::::
. D DO m VAULT 2 RM - RE 6539 s
i i i
~
RHR VAULTS at EL (-161'- 0" A l B l C l D l E l F ALL I ALL ALL i ALL Time Dose Rate Dose Rate Smear Airbome lodine Part mR/hr l mR/hr i mR/hr mR/hr i mR/hr i mR/hr com I uCi/cc com I com 18 23 22 1 20 l 14 .<100 12.11E-10 As Read i 27 8:00 8 l- I Al count rates are net epm. All air samples assume a 20 cubic ft volume. 4 10.2.1.23
[1, 1 ., I NEW HAMPSHIRE YANKEE SEABROOK STATION
~
1989 GRADED EXERCISE . 10.1 INPL ANT DATA 10.1.3 RDMS DURING EXERCISE
ANNUALEXERCESE, Revision 2.0 Containment Containment Containment Containment AM106 AM107 13105 AH104 POST LOCA A POST LOCA B PERS HAICH HI PERS HAICH LOW-ALIET 8.00E+00 8.00E+00 4.00E+03 1.00E+01 HIGH .1.00E+01 1.00E+01 1.00E+04 1.00E+02 SCENARIO TIKI R/hr R/hr nR/hr nR/hr 7:30 8.80E-01 7.10E-01 8.36E-01 8.36E-01 7:45 8.80E-01 ' 10E-01 8.36E-01 8.36E-01 8:00 8.80E-01 .10E-01 8.36E-01 8.36E-01 8:15 8.80E-01 7.10E-01 8.36E-01 8.36E-01 8:30 8.80E-01 7.10E-01 8.36E-01 8.36E-01 8:45 8.80E-01 7.10E-01 8.36E-01 8.36E-01 l-9:00 8.80E-01 7.10E-01 8.36E-01 8.36E-01 9:15 8.80E-01 7.10E-01 8.36E-01 8.36E-01 9:30 8.80E-01 7.10E-01 8.36E-01 8.36E-01 9:45 8.80E-01 '.10E-01 8.36E-01 8.36E-01 10:00 8.80E-01 .10E-01 8.36E-01 8.36E-01 10:15 8.80E-01 7.10E-01 8.36E-01 8.36E-01 10:30 9.80E-01 7.91E-01 9.31E-01 9.31E-01 10:45 9.30E-01 7. 9.' F-01 9.31E-01 9.31E-01 11:00 9.80E-01 7.91E-01 9.31E-01 9.31E-01 11:15 9.80E-01 7.91E-01 9.31E-01 9.31E-01 11:30 9.80E-01 .91E-01 9.31E-01 9.31E-01 11:45 9.80E-01 .91E-01 9.31E-01 9.31E-01 12:00 9.80E-01 7.91E-01 9.31E-01 9.31E-01 12:15 9.80E-01 7.91E-01 9.31E-01 9.31E-01 12:30 9.80E-01 7.91E-01 9.31E-01 9.31E-01 12:45 9.80E-01 7.91E-01 9.31E41 9.31E-01 13:00 9.80E-01 ' 91E-01
. 9.31E-01 9.31E-01 13:15 9.80E-01 .91E-01 9. 1E-01 9.31E-01 13:30 9.80E-01 .91E-01 9.31E-01 9.31E-01 13:45 9.80I-01 7.91E-01 9.31E-01 9.31E-01 14:00 9.80E-01 7.91E-01 9.31E-01 9.31E-01 14:15 9.80E-01 7.91E-01 9.31E-01 9.31E-01 14:30 9.80E-01 7.91E-01 9.31E-01 9.31E-01 14:45 9.80E-01 7.91E-01 9.31E-01 9.31E-01 15:00 9.80E-01 7.91E-01 9.31E-01 9.31E-01 15:15 9.80E-01 7.91E-01 9.31E-01 9.31E-01 15:30 9.80E-01 7.91E-01 9.31E-01 9.31E-01 15:45 9.80E-01 7.91E-01 9.31E-01 9.31E-01 16:00 9.80E-01 7.91E-01 9.31E-01 9.31E-01 i
9/20/89,Page10.1.3.1
,y y .
, I i
ANNUALEIEBCISE, Revision 2.0
..RER Vault RHR Vault PR Vault RER Vault AH301. AM303 AM302 AM304 PUNP A LOW PEMP A HI PCMP B LOW . PUNP B EI i ALERI 4.00E+01' 4.00E+01 4.00E'01 4.00E+01 I HIGH 1.00E+02 1.00E+02 1.00E+02 1.00E+02
- - SCENARIO IIME d/hr ~mR/hr '
- :Rihr nR/hr' 7:30 1.80E+01 1.80E+01 '2.00E+01 .2.00E+01 7:45 1.80E+01 '1.80E+01' 2.00E+01 2.00E+01
,c 8:00 -1.80E+01 1.80E+01 2.00E+01 2.00E+01 g 8:15 1.80E+01 1.80E+01 2.00E+01 2.00E+01
.. 8:30 1.80E+01 1.80E+01 2.00E+01 2.00E+01 k 8:45, 1.80E'01L 1.80E+01 2.00E+01 2.00E+01
.9:00 1.80E+01 ~1.80E+01 2.00E+01 2.00E+01 9:15 1.80E+01 -1.80E401 2.00E+01 2.00Et01 9:30' 1.80E+01 - 1.80E+01 2.00E+01 2.00E+01 9:45 '1.80E+01 1.80E+01 2.00E+01 2.00E+01
.10:00 1.80E+01 1.80E+01 2.00E+01 2.00E+01 10:15 1.80E+01 1.80E+01 2.00E+01 '2.00E+01-10:30 1.80E+01 1.80E+01 2.00E+01 2.00E+01 10:45 1.88E+01 1.88E+01 2.00E+01 2.00E+01 11:00 1.88E+01 1.88E+01' 2.00E+01 2.00E+01 11:15 1.88Et01 1.88E+01 2.00E+01 2.00E+01 11:30 1.88E+01 1.88E'01 2.00E+01 2.00E+01 11:45 1.88Et01 1.88E+01 2.00E+01 2.00E+01 12:00 1.88E+01- 1.88E+01 2.00E+01 2.00E+01 12:15 1.88E+01 1.88E+01 2.00E+01 2.00E+01 12:30. 1.88E+01 1.88E+01 2.00E+01 2.00E+01 12:45 1.88E+01 1.88E+01 2.00E401 2.00E+01 13:00 1.88E'01 1.88E+01 2.00E*01 2.00E+01 13:15 1.88E+01 1.88E+01 2.00E+01 2.00E+01 13:30 1.88Et01 1.88E+01 2.00E-01 2.00E+01 13:45 1.88E+01 1.88E+01 2.00E+01 2.00E+01 14:00 1.88E+01 1.88E+01 2.00E+01 2.00E+01 14:15 1.88E+01 1.88E+01 2.00E+01 2.00E+01 14:30 1.88E+01 1.88E+01 2.00E+01 2.00E+01.
14:45 1.88E+01 1.88E+01 2.00E+01 2.00E+01 15:00- 1.88E+01 1.88E+01 2.00E+01 2.00E+01 15:15 1.88E'01 1.88E+01 2.00E+01 2.00E+01 15:30' 1.88E+01 1.88E+01 2.00E+01 2.00E+01 15:45 1.88E'01 1.88E+01 2.00E+01 2.00E+01 16:00 ~1.88E+01 1.88E+01 2.00E+01 2.00E+01 9/20/89,Page10.1.3.2
11 ANNUALEXERCISIiEevision2.0 PAB PAB PAB PAB AM205 AM233 AM234 AM204 25' S LOW "' S LOW 7' S HI 7' N LOW ALEP.T 1.00E+00 2.00E+01 5.00E+01 2.00E+01 i HIGH 2.50E+00 ' 1.00E+02 1.00E+03 1.00E+02 SCENARIO TIME d/hr 2/hr d/hr d/hr 7:30 1.50E-01 4.00E+00 4.00E+00 6.00E+00 7:45 1.50E-01 4.00E+00 4.00E+00 6.00E+00 8:00 1.50E-01 4.00E+00 4.00E+00 6.00E+00 8:15 1.50E-01 4.00E+00 4.00E+00 6.00E+00 8:30 1.50E-01 4.00E+00 4.00E+00 6.00E+00 8:45 1.50E-01 4.00E+00 4.00E+00 5.00E+00 9:00 1.50E-01 4.00E+00 4.00E+00 6.00E+00 9:15 1.50E-01 4.00E+00 4.00E+00 6.00E HX) 9:30 1.50E-01 4.00E+00 4.00E+00 6.00E+00 9:45 1.50E-01 4.00E+00 4.00E+00 6.00E+00 10:00 1.50E-01 4.00E+00 4.00E+00 6.00E+00 10:15 1.50E-01 4.00E+00 4.00E+00 6.00E+00 10:30 1.50E-01 4.00E+00 4.00E+00 6.00E+00 10:45 1.50E-01 4.00E+00 4.00E+00 5.00I+00 11:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 11:15 1.50E-01 4.00E+00 4.00E+00 4.00E+00 11:30 1.50E-01 4.00E'00 4.00E+00 4.00E+00 11:45 1.50E-01 4.00E+00 4.00E400 4.00E+00 12:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 12:15 1.50E-01 4.00E+00 4.00E+00 4.00E+00 12:30 1.50E-01 4.00E+00 4.00E+00 4.00E+00 12:45 1.50E-01 4.00E+00 4.00E+00 4.00E+00 13:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 13:15 1.50E-01 4.00E+00 4.00E+00 4.00E+00 13:30 1.50E-01 4.00E+00 4.00E+00 4.00E+00 13:45 1.50E-01 4.00E+00 4.00E+00 4.00E+00 14:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 14:15 1.50E-01 4.00E+00 4.00E+00 4.00E+00 14:30 1.50E-01 4.00E+00 4.00E+00 4.00E+00 14:45 1.50E-01 4.00E+00 4.00E+00 4.00E+00 15:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 15:15 1.50E-01 4.00E+00 4.00E+00 4.00E+00 15:30 1.50E-01 4.00E+00 4.00E+00 4.00E+00 15:45 1.50E-01 4.00E+00 4.00E+00 4.00E+00 16:00 1.50E-01 4.00E+00 4.00E+00 4.00E+00 9/20/89,Page10.1.3.3 l l
. _ _ _ _ _ _ _ _ _ - _ - _ _ _ - A
ANNUAL IIERCTSE, Revisioll 2.0 PAB PAB PAB PIB AM211 M206 AM210 M207 7' N HI -6' N LO -6' N HI CH PHP A ALERT 5.00E+01 2.00E+01 2.00E+01 1.00E+01 HIG 1.00E+03 1.00E+02 1.00E+02 5.00E+01 SCENARIO TIME d/hr dihr d/hr d/hr 7:30 1.00E+01 9.00E+00 6.00E+00 3.50E+00 7:45 1.00E+01 9.00E-00 6.00E+00 3.50E+00 8:00 1.00E+01 9.00E+00 6.00E+00 3.50E+00 8:15 1.00E+01 9.00E+00 6.00E+00 3.50E+00 8:30 1.00E+01 9.00E+00 6.00E+00 3.50E+00 8:45 1.00E+01 9.00E+00 6.00E+00 3.50E+00 9:00 1.00E+01 9.00Et00 6.00E+00 3.50E+00 9:15 1.00E+01 9.00E+00 6.00E+00 3.50E+00 9:30 1.00E+01 9.00E+00 6.00E+00 3.50E+00 9:45 1.00E+01 9.00E+00 6.00E+00 3.50E+00 10:00 1.00E+01 9.00E+00 6.00E+00 3.50E+00 10:15 1.00E+01 9.00E+00 6.00E+00 3.50E+00 10:30 1.00E+01 9.00E+00 6.00E+00 3.50E+00 10:45 1.00E+01 9.00E+00 6.00E+00 3.50E+00 11:00 9.00E+00 8.00E+00 6.00E+00 3.50E+00 11:15 8.00E+00 .00Et00 6.00E+00 3.50E+00 11:30 8.00E+00 7.00E+00 6.00E+00 3.50E+00 11:45 8.00E+00 .00E-00 6.00E*00 3.50E+00 12:00 8.00E+00 7.00E+00 6.00E+00 3.50E+00 12:15 8.00E+00 7.00Et00 6.00E+00 3.50E+00 12:30 8.00E+00 7.00E+00 6.00E+00 3.50E+00 12:45 8.00E+00 7.00E+00 6.00E+00 3.50E+00 14:00 8.00E+00 7.00E+00 6.00E+00 3.50E+00 13:15 8.00E+00 ' 00Et00
. 6.00E+00 3.50E+00 13:30 8.00E+00 7.00E+00 6.00E+00 3.50E+00 1 13:45 8.00E+00 7.00E+00 6.00E+00 3.50E+00 14:00 8.00E+00 7.00E+00 6.00E+00 3.50E+00 14:15 8.00E+00 7.00E+00 6.00E+00 3.50E+00 14:30 8.00E+00 7.00E+00 6.00E+00 3.50E+00 14:45 8.00E+00 7.00E+00 6.00E+00 3.50E+00 15:00 8.00E+00 7.00E+00 6.00E+00 3.50E+00 15:15 8.00E+00 7.00E+00 6.00E+00 3.50E+00 15:30 8.00E+00 7.00E+00 6.00E+00 3.50E+00 15:45 8.00E+00 "'.00E+00 6.00E+00 3.50E+00 16:00 8.00E+00 7.00E+00 6.00E+00 3.50E+00 ,
1 9/20/89,Page10.1.3.4
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i 1
-I ANNUALEXERCISE.-Revision 2.0 PIB PAB -I AM208 AM209 AM232 'AM2294
.CH PKP B CH PHP 128 ' CT SAMP.EM*
ALERT 2.50E+01 2.00E+01 '5.00E+03 5.00E+00 HIGH 5.00E+01 5.00E+01 2.00E+04 1.00E+01 SCENARIO TIME mR/hr mR/hr nRihr aR/hr i 7:30 , 2.00E+01 8.00E+00 7.20E+01 1.50E-01 - 7:45 2.00E+01 8.00E+00 7.20E+01 1.50E-01 8:00 2.00E+01- 8.00E+00 '.20E+01 1.50E : 8:15 2.00E+01' 8.00E+00 7.20E+01 1.50E-01. 8:30 2.00E+01 8.00E+00 7.20E+01 1.50E-01. 1 8:45 2.00E+01- 8.00E+00 7.20E+01 1.50E-01 9:00 -2.00E+01 8.00E+00 7.20E+01' 1.50E-01 l 9:15. 2.00E+01'- 8.00E+00- 7.20E+01 1.50E-01 9:30 2.00E+01 8.00E+00 ' 20E+01
. 1.50E-01 9:45- 2.00E+01 8.00E+00 7.20E+01 1.50E-01 10:00- 2.00E+01 8.00E+00 1.20E+01 : 1.50E-01 10:15 2.00E+01 8.00E+00 7.20E+01 1.50E-01 10:30. 2.00E+01 -8.00E+00 7.20E+01 1.50E-01 10:45 2.00E+01' 8.00E+00 7.20E+01 1.50E-01 11:00 2.00E+01- 8.00E+00 3.65E+01 1.50E-01 11:15 '1.70E+01 8.00E+00 2.65E+01 1.50E-01 11:30 1.20E+01 8.00E+00 2.31E'01 1.50E-01 11:45 1.20E+01 8.00E+00 2.31E'01 1.50E-01 12:00 1.20E+01 8.00E+00 2.31E+01 1.50E-01
-12:15 1.20E+01 8.00E+00 2.31E+01 1.50E-01 12:30 1.20E+01 8.00E+00 2.31E+01 1.50E-01 12:45 1.20E+01 8.00E+00 2.31E+01 1.50E-01 13:00 1.20E+01 8.00E+00 2.31E401 1.50E-01 13:15- 1.20E+01 8.00E+00 2.31E+01 1.50E-01 13:30 1.20E+01 8.00E+00 2.31E'01 1.50E-01 13:45 1.20E+01 8.00E+00 2.31E+01 1.50E-01 l 14:00 1.20E+01 8.00E+00 2.31E+01 1.50E-01 l; 14:15 1.20E+01 8.00E+00 2.31E+01 1.50E-01 14:30, 1.20E+01 8.00E+00 2.31E+01 1.50E-01 l 14:45 1.20E+01 8.00E+00 2.31E+01 1.50E-01 15:00 1.20E+01 8.00E+00 2.31E+01 1.50E-01 15:15 1.20E+01 8.00E+00 2.31E'01 1.50E-01 15:30 1.20E+01 8.00E+00 2.31E+01 1.50E-01 15:45 1.20E+01 8.00E+00 2.31E+01 1.50E-01
'16:00' 1.20E+01 8.00E+00 2.31E+01 1.50E-01
- Note 0.3 mR/hr during sampling.
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ANNUALEXE2ClSE, Revision 2.0 Admin. Bldg. Control Room ' Containment Containment AM703 AM501 AP111 NG101 MAINT SHOP CR AREA PARTICULATE GAS ALERI 1.00E+00 1.00E+00 1.00E-07 5.00E-04 HIGH 2.50E+00 2.50E+00 1.00E-09 5.00E-03 SCENARIO IIMI mR/hr cR/hr UCi.cc uCi/cc
":30 1.50E-01 1.50E-01 9.30E-10 9.80E-06
*:45 1.50E-01 1.50E-01 9.30E-10 9.80E-06 8:00 1.50E-01 1.50E-01 9.30E-10 9.80E-06 8:15 1.50E-01 1.50E-01 9.30E-10 9.80E-06 8:30 1.50E-01 1.50E-01 9.30E-10 9.80E-06 8:45 1.50E-01 1.50E-01 9.30E-10 9.80E-06 9:00 1.50E-01 1.50E-01 9.30E-10 9.80E-06 9:15 1.50E-01 1.50E-01 9.30E-10 9.80E-06 9:30 1.50E-01 1.50E-01 9.30E-10 9.80E-06 9:45 1.50E-01 1.50E-01 9.30E-10 9.80E-06 10:00 1.50E-01 1.50E-01 9.30E-10 9.80E-06 10:15 1.50E-01 1.50E-01 9.30E-10 9.80E-06 10:30 1.50E-01 1.50E-01 9.30E-10 9.80E-06 10:45 1.50E-01 1.50E-01 9.30E-10 9.80E-06 11:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 11:15 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 11:30 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 11:45 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 12:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 12:15 1.50E-01 1.50E-01 9.30E-10 = 9.80E-06
- 12:30 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 12:45 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 13:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 13:15 1.50E-01 1.50E-01 9.30E-10 a 9.80E-06
- 13:30 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 13:45 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 14:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 14:15 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 14:30 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 14:45 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 15:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 15:15 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 15:30 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 15:45 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06
- 16:00 1.50E-01 1.50E-01 9.30E-10
- 9.80E-06 *
- A I455 OE ELOW ALARM occurs at 11:00 AH. These instruments remain isolated from 11:00 AM to drill end. Monitors remains in alarm due to loss of flow.
9/20/89,Page10.1.3.6
ANNUAL EXERCISE, Revision 2.0 Containment PAB PAB WRGM GA112 GA273 CA274 NG222 ENCL EM El CONT ENCL MISC "ENT LOW ALERT 5.00E+01 5.00E+01 5.00E+01 4.00E-06 i HIGH 1.00E+02 1.00E+02 1.00E+02 1.00E-05 l SCENARIO TIMI CPM CPM CPM uCi/cc 7:30 2.24E+00 2.31E+01 3.10E+01 2.66E-06 7:45 2.24E+00 2.31E+01 3.10E+01 2.66E-06 8:00 2.24E+00 2.31E+01 3.10E+01 2.66E-06 8:15 2.24E+00 2.31E+01 3.10E+01 2.66E-06 l 8:30 2.24E+00 2.31E+01 3.10E+01 2.66E-06 8:45 2.24E+00 2.31E+01 3.10E+01 2.66E-06 , I 9:00 2.24E+00 2.31E+01 3.10E+01 2.66E-06 9:15 2.24E+00 2.31E+01 3.10E+01 2.66E-06 9:30 2.24E+00 2.31E+01 3.10E+01 2.66E-06 9:45 2.24E+00 2.31E+01 3.10E+01 2.66E-06 10:00 2.24E+00 2.31E+01 3.10E+01 2.66E-06 < 10:15 2.24E+00 2.31E+01 3.10E+01 2.66E-06 10:30 2.24E+00 2.31E+01 3.10E+01 2.66E-06 ,l 10:45 2.24E+00 2.31E+01 3.10E+01 2.66E-06 11:00 2.24E+00 2.31E+01 3.10E+01 2.66E-06 11:15 2.27E+00 2.31E+01 3.10E+01 2.66E-06 11:30 2.31E+00 2.31E+01 3.10E+01 2.66E-06 11:45 2.34E+00 2.31E+01 3.10E+01 2.66E-06 12:00 2.38E+00 2.31E+01 3.10E+01 2.66E-06 12:15 2.41E+00 2.31E+01 3.10E+01 2.66E-06 12:30 2.45E+00 2.31E+01 3.10E+01 2.66E-06 12:45 2.49E+00 2.31E+01 3.10E+01 2.66E-06 13:00 2.52E+00 2.31E+01 3.10E+01 2.66E-06 13:15 2.56E+00 2.31E+01 3.10E+01 2.66E-06 13:30 2.60E+00 2.31E+01 3.10E+01 2.66E-06 13:45 2.64E+00 2.31E+01 3.10E+01 2.66E-06 14:00 2.68E+00 2.31E+01 3.10E+01 2.66E-06 14:15 2.72E+00 2.31E+01 3.10E+01 2.66E-06 14:30 2.76E+00 2.31E+01 3.10E+01 2.66E-06 14:45 2.80E+00 2.31E+01 3.10E+01 2.66E-06 15:00 2.84E+00 2.31E+01 3.10E+01 2.66E-06 15:15 2.89E'00 2.31E+01 3.10E+01 2.66E-06 15:30 2.93E+00 2.31E+01 3.10E+01 2.66E-06 15:45 2.97E+00 2.31E+01 3.10E+01 2.66E-06 16:00 3.02E+00 2.31E+01 3.10E+01 2.66E-06 NOTE: On WRGM Channels NG222, NG223 and NG224 the alarm setpoints indicate range changes only. CONTROLLERS should NOT issue alarm status' for these monitors. 9/20/89,Page10.1.3.7
p [ 'ANNUALEXIRCISE, Revision 2.0 WRGM WRGH . RGM W ControlRoomAir NG223 NG224 CC225 GA510 MID' 'HI EFTL TRAN A .. EAST
' ALERT' 1.00E-03 ;.1.00E-01 2.74E+03 5.00E+01 EIGH 2.00E-03. 2.00E 2.74E+05 1.00E+02 SCENARIO TIME- uCi/cc uCi/cc uC1/sec CPM 7:30 1.00E-04 '1.00E-02 1.51E+02 1.62E+01 7:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 8:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 8:15- 1.00E 1.00E-02 ,
1.51E+02 1.62E+01
.8:30' 1.00E-04 1.00E-02 1.51E+02 1.62E+01 8:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 9:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 9:15 .1.00E-04 1.00E-02 1.51E+02 1.62E+01 9:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 9:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 10:00- 1.00E-04 1.00E-02 1.51E+02 1.62E+01 10:15 1.00E-04 1.00E-02 1.51E+02 1.62E+01 10:30 .1.00E-04 1.00E-02 1.51E+02 1.62E+01-10:45' 1.00E-04 '1.00E-02 1.51E+02 1.62E+01 11:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 11:15 1.00E-04 1.00E-02 1.51E+02 1.62E+01 11:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 11:45 1.00E-04 1.00E-02 1.51E+02 1.62E-01 12:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 12:15 1.00E-04 1.00E-02 1.51E+02 1.62E+01 12:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 12:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 13:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 13:15 1.00E-04 1.00E-02 1.51E+02 :1.62E+01 13:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 13:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 14:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 14:15 1.00E-04 1.00E-02 1.51E+02 1.62E+01 14:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 14:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 15:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 15:15 1.00E-04 1.00E-02 1.51E+02 1.62E+01 15:30 1.00E-04 1.00E-02 1.51E+02 1.62E+01 15:45 1.00E-04 1.00E-02 1.51E+02 1.62E+01 16:00 1.00E-04 1.00E-02 1.51E+02 1.62E+01 NOTE:OnWRGHChannelsNG222,NG223andNG224thealarmsetpointsindicaterangechanges only.CONTROLLERSshouldNOTissuealarmstatus'forthesemonitors.
l I 9/20/89,Page10.1.3.8 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ________________________________________________J
y A!GCALEXERC8SE, Revision 2.0 Control Roon Air ControlRoonAir . Control Roon Air- MainSteasLine
~
GA511 CA520 G1521 GM801 TP).N A ' WEST TP).N B EAST TRAN B ' kT.ST LOOP 1 ALERT 5.00E+01 5.00E+01 5.00E'01 5.00I-01 HIGH 1.00E+02 1.00E+02 1.00E+02 5.00E+00 SCENARIO TIME ' CPM CPM ' CPM . mR/hr 7:30 1.92E+01 1.94E+01 1.61E+01- 3.90E-01 -
'7:45- 1.92E+01 1.94E+01 1.61E+01 3.90E-01
, 8:00 1.92E+01 1.94E+01 1.61E+01 3.90E-01 8:15 1.92E+01 1.94E+01 1.61E*01 3.90E-01 8:30 1.92E+01 1.94E+01 1.61E+01 3.90E-01 8:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01 9:00 1.92E+01 1.94E+01 1.61E+01 3.90E-01 9:15 1.92E+01 1.94E+01 1.61E+01 3.90E-01 9:30 1.92E+01- 1.94E+01 1.61E+01 3.90E-01 9:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01 10:00- 1.92E+01 1.94E+01 1.61Et01 3.90E-01 10:15 1.92E+01 1.94E+01 1.61E+01 3.90E-01
,10:30 1.92E+01 1.94E+01 1.61E+01 3.90E-01 10:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01 11:00- 1.92E+01 1.94E+0! 1.61E+01 3.90E-01 11:15 1.92E+01 1.94E+01 1.61E+01 3.90E-01
.11:30 1.92E'01 1.94E+01 1.61E+01 3.90E-01 11:45 1.92E'01 1.94E+01 1.61Et01 3.90E-01 12:00~ 1.92E+01 1.94E+01 1.61E+01 3.90E-01 12:15 1.92E+01 1.94E+01 1.61E,01 3.90E-01 12:30- 1.92E+01 1.94E+01 1.61E+01 3.90E-01 12:45 - 1.92E+01 1.94E+01 1.61Et01 3.90E-01 13:00 1.92E+01 1.94E+01 1.61E+01 3.90E-01 13:15 1.92E+01 1.94E+01 1.61E-01 3.90E-01 13:30 1.92E+01 1.94E+01 1.61E+01 3.90E-01 13:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01 14:00 1.92E+01 1.94E+01 1.61E+01 3.90E-01 14:15' 1.92E+01 1.94E+01 1.61E+01 3.90E-01 14:30 1.92E+01 1.94E+01 1.61E+01 3.90E-01 14:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01 15:00 1.92E+01- 1.94E+01 1.61E+01 3.90E-01 15:15 1.92E+01 1.94Et01 1.61E+01 3.90E-01 15:30 1.92E+01 1.94E+01 1.61E+01 3.90E-01 15:45 1.92E+01 1.94E+01 1.61E+01 3.90E-01
-16:00 1.92E+01 1.94E+01 1.61E+01 3.90E-01 9/20/89,Page10.1.3.9
j l ANNUAL IIEDCISE, Revision 2.3 I i MainSteamLine MainSteamLine Main Steam Line Reactor Coolant CM803 CM804 'CM802 LM240 LOOP 2 LOOP 3
)
LOOP 4 LETDN LOW / ALERT 5.00E-01 5.00E-01 5.00E-01 1.39E+01 EIG 5.00E+00 5.00E+00 5.00E+00 5.56E+01 j SCENARIO TIEE tR/hr tR/hr tR/hr uCi/ml
~ :30 3.90E-01 3.90E-01 3.90E-01 2.15E-03 7:45 3.90E-01 3.90E-01 3.90E-01 2.15E-03 i 8:00 3.90E-01 3.90E-01 3.90E-01 2.15E-03 8:15 3.90E-01 3.90E-01 3.90E-01 2.15E-03 8:30 3.90E-01 3.90E-01 3.90E-01 2.15E-03 8:45 3.90E-01 3.90E-01 3.90E-01 2.15E-03 9:00 3.90E-01 3.90E-01 3.90E-01 2.15E-03 9:15 3.90E-01 3.90E-01 3.90E-01 2.15E-03 9:30 3.90E-01 3.90E-01 3.90E-01 2.15E-03 9:45 3.90E-01 3.90E-01 3.90E-01 2.15E-03' 10:00 3.90E-01 3.90E-01 3.90E-01 2.15E-03 10:15 3.90E-01 3.90E-01 3.90E-01 2.15E-03 10:30 3.90E-01 3.90E-01 3.90E-01 2.15E-03 10:45 3.90E-01 3.90E-01 3.90E-01 2.15E-03 11:00 3.90E-01 3.90E-01 '3.90E-01 2.15E-03 11:15 3.90E-01 3.90E-01 3.90E-01 2.09E-03 11:30 3.90E-01 3.90E-01 3.90E-01 2.06E-03 11:45 3.90E-01 3.90E-01 3.90E-01 2.02E-03 12:00 3.90E-01 3.90E-01 3.90E-01 1.93E-03 12:15 3.90E-01 3.90E-01 3.90E-01 1.83E-03 12:30 3.90E-01 3.90E-01 3.90E-01 1.80E-03 12:45 3.90E-01 3.90E-01 3.90E-01 1.79E-03 13:00 3.90E-01 3.90E-01 3.90E-01 1.73I-03 13:15 3.90E-01 3.90E-01 3.90E-01 1.66E-03 13:30 3.90E-01 3.90E-01 3.90E-01 1.65E-03 13:45 3.90E-01 3.90E-01 3.90E-01 1.57E-03 14:00 3.90E-01 3.90E-01 3.90E-01 1.54E-03 14:15 3.90E-01 3.90E-01 3.90E-01 1.51E-03 I 14:30 3.90E-01 3.90E-01 3.90E-01 1.48E-03 14:45 3.90E-01 3.90E-01 3.90E-01 1.46E-03 15:00 3.90E-01 3.90E-01 3.90E-01 1.37E-03 15:15 3.90E-01 3.90E-01 3.90E-01 1.32E-03 15:30 3.90E-01 3.90E-01 3.90E-01 1.27E-03 15:45 3.90E-01 3.90E-01 3.90E-01 1.27E-03 16:00 3.90E-01 3.90E-01 3.90E-01 1.19E-03 l
1 9/20/89,Page10.1.3.10 l
i ANNUALEXERCISE. Revision 2.0 Reactor Coolant Reactor Coolant k'PB k'PB LH241 LK242 AM602 AH606 LETDN HI LETDN ACTO . TRUCK BAY C0KPACTOR ALEIT 1.39E+01 1.39E+01 2.50E+00 2.50E+00 HIGH 5.56E+01 5.56E+01 1.00E+01 1.00E+01 SCENARIO TIME uCi/nl uCi/ml tR/hr nR/hr 7:30 2.15E-03 2.15E-03 2.00E-01 3.00E-01 7:45 2.15E-03 2.15E-03 2.00E-01 3.00E-01 8:00 2.15E-03 2.15E-03 2.00E-01 3.00E-01 8:15 2.15E-03 2.15E-03 2.00E-01 3.00E-01 8:30 2.15E-03 2.15E-03 2.00E-01 3.00E-01 8:45 2.15E-03 2.15E-03 2.00E-01 3.00E-01 9:00 2.15E-03 2.15E-03 2.00E-01 3.00E-01 9:15 2.15E-03 2.15E-03 2.00E-01 3.00E-01 9:30 2.15E-03 2.15E-03 2.00E-01 3.00E-01 9:45 2.15E-03 2.15E-03 2.00E-01 3.00E-01 10:00 2.15E-03 2.15E-03 2.00E-01 3.00E-01 10:15 2.15E-03 2.15E-03 2.00E-01 3.00E-01 10:30 2.15E-03 2.15E-03 2.00E-01 3.00E-01 10:45 2.15E-03 2.15E-03 2.00E-01 3.00E-01 11:00 2.15E-03 2.15E-03 2.00E-01 3.00E-01 11:15 2.09E-03 2.09E-03 2.00E-01 3.00E-01
~11:30 2.06E-03 2.06E-03 2.00E-01 3.00E-01 11:45 2.02E-03 2.02E-03 2.00E-01 3.00E-01 12:00 1.93E-03 1.93E-03 2.00E-01 3.00E-01 12:15 1.83E-03 1.83E-03 2.00E-01 3.00E-01 12:30 1.80E-03 1.80E-03 2.00E-01 3.00E-01 12:45 1.79E-03 1.79E-03 2.00E-01 3.00E-01 13:00 1.73E-03 1.73E-03 2.00E-01 3.00E-01 13:15 1.66E-03 1.665-03 2.00E-01 3.00E-01 13:30 1.65E-03 1.65E-03 2.00E-01 3.00E-01 13:45 1.57E-03 1.57E-03 2.00E-01 3.00E-01 14:00 1.54E-03 1.54E-03 2.00E-01 3.00E-01 14:15 1.51E-03 1.51E-03 2.00E-01 3.00E-01 14:30 1.48E-03 1.48E-03 2.00E-01 3.00E-01 14:45 1.46E-03 1.46E-03 2.00E-01 3.00E-01 15:00 1.37E-03 1.37E-03 2.00E-01 3.00E-01 15:15 1.32E-03 1.32E-03 2.00E-01 3.00E-01 j 15:30 1.27E-03 1.27E-03 2.00E-01 3.00E-01 l 15:45 1.27E-03 1.27E-03 2.00E-01 3.00E-01 16:00 1.19E-03 1.19E-03 2.00E-01 3.00E-01 l
9/20/89, Page 10.1.3.11
L'E '
'1NNUAL D:E2CfSE, Revisloh 2.0-E WPB- WPB. k'PB WPB
- AP610 NG611 CC612- AN601 WPB PART. . WPB GAS WPB EITLCENT : GAS PROCESSING.
. ALERT 1.00E-09 5.00E 0.00E+00 2.50E+00
'HIGH 2.25E-09 1.00E-05 0.00E+00 1.00E+01 SCENARIOTIME- uCi/t1 uCi/t1 uCl/sec mR/hr v
L 7:30 -1.01E-10 7.80E-07 5.90E+01- 3.00E-01 - 7:45 1.01E-10 7.80E-07 5.90E+01 3.00E-01 8:00 .1.01E-10 7.80E-07 5.90E+01 3.00E-01
- 8:15 1.01E-10 7.80E-07 5.90E+01 3.00E-01'.
p _8:30 .1.01E-103 7.80E-07 5.90E+01 -3.00E-01 8:45- 1.01E-10 7.80E-07 5.90E+01 3.00E-01 9:00 1.01E-10 -7.80E-07. 5.90E+01- 3.00E-01 9:15 1.01E 7.80E-07 5.90E+01 3.00E '9:30- 1.01E-10' 7.80E-07l 5.90E+01 3.00E-01 9:45 1.01E-10 7.80E-07 5.90E+01- 3.00E-01
'10:00 1.01E '7.80E-07 5.90E+01 3.00E-01 10:15' 1.01E-10 7.80E-07 5.90E+01 '3.00E-01 10:30 1.01E-10 7.80E-07 5.90E+01 3.00E-01 10:45- 1.01E-10 7.80E-07 5.90E+01 3.00E-01 11:00~ 1.01E-10 ' 80E-07 5.90E+01 3.00E-01 11:15- 1.01E ~.80E-07 5.90E+01 3.00E-01 11:30 1.01E ".80E-07 5.90E+01 3.00E-01 11:45 1.01E-10 ' .80E-07 5.90E+01 3.00E-01 12:00' 1.01E-10 7.80E-07 5.90E+01 3.00E-01 12:15'- 1.01E-10 7.80E-07 5.90E+01 3.00E-01 12:30 1.01E-10 7.80E-07 5.90E+01 3.00E-01 12:45' 1.01E-10 7.80E-07 5.90E+01 3.00E-01
.13:00' 1.01E-10 '.80E-07 5.90E+01 3.00E-01 13:15- 1.01E-10 .80E-07 5.90E+01 .3.00E-01 13:30 1.01E-10 7.80E-07 5.90E+01 3.00E-01
- 13:45 1.01E-10 '.80E-07 5.90E+01 3.00E-01 14:00 1.01E-10 7.80E-07 5.90E+01 3.00E-01 14:15' 1.01E-10 7.80E-07 5.90E+01 3.00E-01 14:30 1.01E-10 7.80E-07 5.90E+01 3.00E-01 14:45 1.01E-10 7.80E-07 5.90E+01 3.00E-01
'15:00 1.01E-10 7.80E-07 5.90E+01 3.00E-01
- 15:15 1.01E-10 ' 80E-07
. 5.90E+01 3.00E-01 15:30 1.01E 7.80E-07 5.90E+01 3.00E-01 15:45 1.01E-10 7.80E-07 5.90E*01 3.00E-01 16:00 1.01E-10 7.80E-07 5.90E+01 3.00E-01 9/20/89,Page10.1.3.12
= _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . . _ _ _ .
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y;
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4 ANEAL EXERCISE, R2 Vision 2.0
~
4 '
~
@B- @B- @B CONDENSER h '
AM603 AM604 AM605- GM810-CONTROL ROOH CONTROL PANEL ' :EXTRLDER COND AIR E"AC.
,. ALERT 2.50E+00 2.50E+00 5.00E+01- 6.00E+02 HIGH '1.00E+01 1.00E+01 1.00E+02- 1.00E+03 SCENARIO TIME- mR/hr- ;mR/hr :mR/hr CPM 7:30 2.00E-01 4.00E-01 2.40E+01 2.20E+01 L **:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 8:00- 2.00E-01 4.00E-01 2.40E+01 2.20E+01 8:15- 2.00E-01 -4.00E-01 2.40E+01L -2.20E+01 8:30 2.00E-01 '4.005-01 2.40E+01 2.20E+01 8:45. 2.00E-01 4.00E-01 2.40E+01 2.20E+01 9:00 2.00E-01 4.00E-01 2.40E+01 2.20E+01 9:15 2.00E-01 4.00E-01 2.40E+01 2.20E+01 9:30 2.00E-01 '4.00E-01 2.40E+01 2.20E+01 9:45 2.00E-01 '4.00E-01 -2.40Et01 2.20E+01 10:00 2.00E-01 4.00E ' 2. !0D01 2.20Et01
'10:15l 2.00E 4.00E-01 2.40E+01- 2.20E+01 10:30 2.00E-01 4.00E-01 2.40E+01 2.20E+01 110:45 2.00E-01 4.00E 2.40E+01 2.20E+01 11:00 2.00E-01 4.00E-01 :2.40E+01 2.20E+01-11:15' _2.00E-01'- 4.00E-01 2.40E+01 2.20E+01 11:30 2.00E-01 4.00E-01 2.40E+01 2.20E'01
-11:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 12:00. 2.00E-01 4.00E-01 '2.40E+01 2.20E+01 12:15 2.00E-01 4.00E-01 2.40E+01 2.20E+01 12:30 2.00E-01 4.00E-01 2.40E+01 2.20E+01 12:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 13:00 2.00E-01 4.00E-01 2.40E+01 2.20E+01 13:15 -2.00E ~.00E-01 4 2.40E+01 2.20E+01 13:30 2.00E-01 4.00E-01 2.40E+01 2.20E*01 13:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 14:00 2.00E-01 4.00E-01 .2.40E+01 2.20E+01 l 14:15 2.00E-01 4.00E-01 2.40E+01 2.20E+01 l
14:30 2.00E-01 4.00E-01 2.40E+01 2.20E+01 14:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 15:00 2.00E-01 4.00E-01 2.40E+01 2.20E+01 15:15 2.00E-01 4.00E-01 2.40E+01 2.20E+01 15:30 2.00E-01 4.00E-01 2.40E+01 2.20E+01 15:45 2.00E-01 4.00E-01 2.40E+01 2.20E+01 16:00 2.00E-01 4.00E-01 2.40E+01 2.20E+01 I 9/20/89,Page10.1.3.13 I
A!GUAL EXERCISE, leVision 2.C 1 SG BLOh%7i SG BWh%1 SG BL0i%1 SG DLQh% 1 LK216 LE212 LM213 LK214 LOOP 1 LOOP 2 LOOP 3 LOOP 4 ALERT 2.00E-05 2.00E-05 2.00E-05 2.00E-05 EIGH 1.00E-04 1.00E-04 1.00E-04 1.00E-04 SCENARIO T1XE uCi/ml uCi/ml uCi. nl uCi/ml I 7:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 7:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 8:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 8:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 8:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 8:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 9:00 4.53E-08 4.53E 08 4.53E-08 4.53E-08 0:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 9:30 4.53E-03 4.53E-08 4.53E-08 4.53E-08 9:45 4.53E-08 4.53I-08 4.53E-08 4.53E-08 10:00 4.53E-08 4.53E-08 4.53I-08 4.53E-08 l 10:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 10:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 10:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 11:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 11:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 11:30 4.53E-08 1.53E-08 4.53E-08 4.53E 08 11:45 4.53E-08 4.53E-08 4.53I-08 4.53E-08 12:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 12:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 12:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 12:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 13:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 i 13:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 13:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 13:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 14:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 14:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 14:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 14:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 15:00 4.53E-08 4.53E-06 4.53E-08 4.53E-08 15:15 4.53E-08 4.53E-08 4.53E-08 4.53E-08 15:30 4.53E-08 4.53E-08 4.53E-08 4.53E-08 15:45 4.53E-08 4.53E-08 4.53E-08 4.53E-08 16:00 4.53E-08 4.53E-08 4.53E-08 4.53E-08 9/20/89, Page 10.1.3.14
ANNUALEIERC15E, Revision 2.0 PAB PAB AP270 NG271 PART GAS ALERT 1.00E-09 5.00E-06 i- HIGH 2.25E-09 1.00E-05 SCENARIO 'IKE uCi/ml uCi/ml 7:30. 8.00E-11 8.00E-07 - 7:45. 8.00E-11 8.00E-07 8:00 8.00E-11 8.00E-07 8:15 8.00E-11 8.00E-07 8:30 8.00E-11 8.00E-07 i 8:45 8.00E-11 8.00E-07 9:00 8.00E-11 8.00E-07 9:15 8.00E 8.00E-07 9:30 8.00E-11 8.00E-07 9:45 8.00E-11 8.00E-07 10:00 8.00E-11 8.00E-07 10:15 8.00E-11 8.00E-07 10:30' 8.00E-11 8.00E-07 10:45. 8.00E-11 8.00E-07 11:00 8.00E-11 8.00E-07 11:15 8.00E-11 8.00E-07 11:30 8.00E-11 8.00E-07 11:45 8.00E-11 8.00E-07 12:00 8.00E-11 .8.00E-07 12:15 8.00E-11 8.00E-07 12:30 8.00E-11 8.00E-07 12:45 8.00E-11 8.00E-07 13:00 8.00E-11 8.00E-07 13:15 8.00E-11 8.00E-07 13:30 8.00E-11 3.00E-07 13:45 8.00E-11 8.00E-07 1 14:00 8.00E-11 8.00E-07 14:15 8.00E-11 8.00E-07 14:30 8.00E-11 8.00E-07 14:45 8.00E-11 8.00E-07 15:00 8.00E-11 8.00E-07 15:15 8.00E-11 8.00E-07 15:30 8.00E-11 3.00E-07 15:45 8.00E-11 8.00E-07 16:00 8.00E-11 8.00E-07 l 9/20/89,Page10.1.3.15
NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 10.1 INPL ANT DAT A 10.1 A SURVEY MAPS AND DOSE RATES DURING EXERCISE l i 1 l I L.
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( <1 (100 2.11E-11 As Read As Read 12:45 <1 <1 <1 (1 (100 2.11E-11 As Read As Read 13:00 <1 <1 <1 (1 <100 2.11E-11 As Read As Read 13:15 <1 (1 <1 <1 (100 2.11E-11 As Read As Read 13:30 (1 <1 <1 <1 <100' 2.11E-11 As Read As Read 13:45 <1 (1 <1 (1 <100 2.11E-11 As Read As Read 14:00 <1 <1 (1 (1 (100 2.11E-11 As Read As Read 14:15 <1 - <1 <1 <1 <100 2.11E-11 As Read As Read 14:30 <1 <1 <1 <1 <100 2.11I-11 As Read As Read 14:45 <1 <1 <1 (1 (100 2.11E-11 As Read As Read 15:00 <1 <1 (1 <1 (100 2.11E-11 As Read As Read 15:15 <1 <1 <1 <1 (100 2.11E-11 As Read As Read 15:30 <1 <1 <1 <1 <100 2.11E-11 As Read As Read 15:45 <1 <1 <1 <1 <100 2.11E-11 As Read As Read 16:00 <1 <1 (1 (1 - (100 2.11E-11 As Read As Read All count rates are net cps. Allairsasolesassumea20cubicftvolume. 7/22/89,Page10.1.4.1 l --
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ANNUAL EXERCISE, Revision 0 TURBINE BLDG. at EL. 75' - 0" A l B l C l D E F ALL ALL ALL ALL Time Dose Rate Snear Airborne Iodine Part. tR/hr tR/hr tR/hr tR/hr tR/hr ER/hr ept UCi/cc eps eps l All <1 (1 <1 <1 <1 <1 (100 1.3E-10 As Read 16 TURBINE BLDG. at EL. 50' - 0" A l B l C l D E F ALL ALL ALL ALL Time Dose Rate Smear Airborne Iodine Part. tR/hr tR/hr tR/hr ER/hr tR/hr tR/hr cps uCi/cc cpt eps All <1 (1 <1 <1 (1 (1 <100 1.1E-10 As Read 14 I TURBINE BLDG. at EL. 21' - 0" A l B l C l D E F ALL ALL ALL ALL Time Dose Rate Snear Airborne Iodine Part. tR/hr tR/hr tR/hr tR/hr tR/hr ER/hr cps uCi/cc cpa cpm All (1 (1 (1 (1 <1 (1 (100 1.2E-10 As Read 15 CONTROL BLDC. at EL. 75' - 0" A l B l C l D E F ALL ALL ALL ALL Time Dose Rate Snear Airborne Iodine Part. tR/hr tR/hr tR/hr ER/hr tR/hr mR/hr cpa uCi/cc cpm cpa l All <1 (1 <1 <1 <1 <1 (100 1.0E-10 As Read 13 All count rates are net cpm. All air saroles assume a 20 cubic ft volume. h i 7/22/89,Page10.1.4.2
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R B VAULTS at EL. :-161' - 0" A l- B C D l l l E l F ALL l ALL ALL ALL l Tine Dose Rate Dose Rate Saear Airborne Iodine Part. nR/hr l mRehr l mR/hr mR/hr l mR/hr l mR/hr cpa l UCi/cc CDs l cpa 1:00 8 - 18 23 22 .20 14 c100 2.11E-10 As Read 27 l 9:00 8- 18 , 23 22 20 14 (100~ 2.11E-10 As Read 27 10:00 18 23 22 20-14 (100 2.11E-10 As Read 27 10:30 8 18 23 22 20
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RER *iACLTS at EL. :-150' - 0" A l 'B l C l D l E l F ALL l- ALL ALL l ALL - Time Dose Rate Dose Rate Satar Airborne Iodine Part. I mR/hr l mR/hr l mR/hr -l mR/br l mR/hr l mR/hr cpa l UCi/cc- cpa l cpa 8:00 9 19 27 35 32 47 (100 2.11E-10 As Read 27 9:00 9' 19 27 35 32' 47 (100- 2.11E-10 As Read 27 10:00 9' ~ 19 . '27 35 32 47 -(100 2.11E-10 As Read 27-10:30 9
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RER '.'AULTS at EL. :-i 9' -0", t-i 16' - 0" A l B l C l D l E l T ALL l ALL ALL ALL l Time Dose Rate- Dose Rate Seear Airborne Iodine Part. aR/hr j mR/hr } nR/hr tRlhr l mRihr l mR/hr cpa j UCi/cc cpa l cpa 8:00 8 19 25 24 27 29 <100 2.11E-10 .As Read 27-9:00 8- 19 _,25 ' 24 27 29 (100 2.11E-10 As Read 27- -[ 10:00 '8 19 25 24 27 29, <100 2.11E-10 As Read 27 - 10:30 8 , 19 25 24 27 29 (100 2.11E-10 As Read 27 10:45 8 19 25 24 27 29 (100 2.11E-10 As Read 27' 11:00 8 19 25 24 27 29 (100 2.11E-10 As Read 27 11:15 8 19 25 24 27 29 <100 2.11E-10 As Read 27 , 11:30 8 - 19 25 24 27 29 <100 2.11E-10 As Read 27 11:45 8 19 25 24 27 29 <100 2.11E-10 As Read 27 12:00 8 19 ' 25 24 27 29 (100 2.11E-10 As Read' 27 12:15 6 19 25 24 27 29 <100 2.11E-10 As Read J 27 12:30 ,8 19 25 24 27 29 <100 2.11E-10 As Read 27 12:45 8 19 25 24 27 29 (100 2.11E-10 As Read 27 13:00 8 19 25 ' 24 27 29 <100 2.11E-10 As Read 27 13:15 8 19 25 24 27 29 (100 2.11E-10 As Read 27 13:30 8 19 25 24 27 29 <100 2.11E-10 As Read 27 13:45 8 19 25 24 27 29 <100 2.11E-10 As Read 27 14:00 8- 19 25 24 27 29 (100 2.11E-10 As Read 27 14:15 '8 19 25 24 27 29 (100 2.11E-10 As Read 27 14:30 8 19: ' 25 24 27 29 <100 2.11E-10 As Read 27-14:45 8 19 25 24 27 29 (100 2.11E-10 As Read 27 15:00 8 19 25 24 27 29 <100 2.11E-10 As Read 27 ', 15:15 8 19 25 24 27 29 (100 2.11E-10 As Read 27 15:30 8 19 25 24 27 29 <100 2.11E-10 As Read 27 15:45 8 19 25- 24 27 29 (100 2.11E-10 As Read 27 ~ 16:00 8 19 25 24 27 29 <100 2.11E-10 As Read 27 All count rates are net cps. All air samples assume a 20 cubic ft volume. i I 7/22/89,Page10.1.4.5 l ___ ____-_______________________D
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I ABUALEXERCISE,R: vision 0 PR VAULTS at EL. 1-131-0" 1 l B l C l D l E- l E ALL l ALL ALL l ALL {__ Tine Dose Rate Dose Rate Smear Airborne Iodine Part. aR/hr l mR/hr j mR/hr l arthr -l mR/hr l'mR/hr cpu l uC1/cc cpm l= cps 8:00 8 19 25 23 33 29 (100 2.11E-10 As Read 27 ; 9:00 8 19 25 23 33 29 <100' 2.11E-10 As Read 27 10:00 8 19 "25 23 33 29 : <100 2.11E-10 As Read 27 10:30 8 19 25 23 33 29 ' (100' 2.11E-10 As Read 27 10:45 8
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I ANNUALEXERCESI, Revision 0 PB VAULTS at EL. O' - 1/2", & 3' - 2" A l B l C l D l E l F ALL l ALL ALL ALL l Time Dose Rate Dose Rate Snear Airborne lodine Part. mR/hr l mR/hr l'mR/hr l mR/br j mR/hr l mR/hr cpa l uCi/cc epa l cps 8:00 9 20 ' 25 34 36 33 (100 2.11E-10 As Read 27 9:00 9 20 25 34 36 33 < 100 2.11E-10 As Read 27
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10:00 9 20 25 34 36 33 (100 2.11E-10 As Read 27 10:30 9 , 20 25 34 36 33 <100 2.11E-10 As Read 27 10:45 9 20 25 34 36 33 (100 2.11E-10 As Read 27 11:00 9 20 25 34 36 33 (100 2.11E-10 As Read 27 11:15 9 20 25 34 36 33 (100 2.11E-10 As Read 27 11:30 9 20 25 34 36 33 (100 2.11E-10 As Read 27 11:45 9 20 25 34 36 33 <100 2.11E-10 As Read 27 12:00 9 20 25 34 36 33 <100' 2.11E-10 As Read 27 12:15 9 20 25 34 36 33 <100 2.11E-10 As Read 27 12:30 9 20 25 34 36 33 (100 2.11E-10 As Read 27 12:45 .9 20 25 34 36 33 <100 2.11E-10 As Read 27 13:00 9 20 25 34 36 33 <100 2.11E-10 As Read 27 13:15 9 20 25 34 36 33 <100 2.11E-10 As Read 27 13:30 9 20 25 34 36 33 <100 2.11E-10 As Read 27 13:45 9 20 25 34 36 33 <100 2.11E-10 As Read 27 14:00 9 20 25 34 36 33 (100 2.11E-10 As lead 27 14:15 9 20 25 34 36 33 <100 2.11E-10 As Read 27 ; 14:30 9 20 25 34 36 33 (100 2.11E-10 As Read 27 14:45 9 20 25 34 36 33 (100 2.11E-10 As Read 27 15:00 -9 20 25 34 36 33 (100 2.11E-10 As Read 27 15:15 9 20 25 34 36 33 <100 2.11E-10 As Read 27 15:30 9 20 25 34 36 33 (100 2.11E-10 As Read 27 15:45 9 20 25 34 36 33 <100 2.11E-10 As Read 27 16:00 9 20 25 34 36 33 (100 2.11E-10 As Read 27 Allcountratesarenetcps. All air samples assume a 20 cubic ft volume. l 1 5 7/22/89,Page10.1.4.7
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6 110lUAL EXERC8SE, Revision 0 PB VAULT STAIRWAY A l B l -C l D l E l r ALL l ALL ALL l ALL Time Dose Rate Dose Rate Smear Airborne Iodine Part. mR/hr l mR/hr l mR/hr l-mR/hr l mR/hr l mR/hr cpu l uCi/cc cpr l cpa 8:00 6 9 15 27 33 37 (100 2.11E-10 As Read 27 9:00 6 9 15 27 33 37 (100' 2.11E-10 As Read 27 10:00 6 9 15 27 33 37 <100 2.11E-10 As Read 27 10:30 6 9 '15 27 33 37 (100 2.11E-10 As Read 27 10:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27. 11:00 6 9 15 27 33 37 (100 2.11E-10 As Read 27 11:15 6 9 15 27 33 37 <100 2.11E-10 As Read 27 11:30 6 9 15 27 33 37 <100 2.11E-10 As Read 27 11:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27 12:00 6 9 15 27. - 33 37 (100 2.11E-10 As Read 27 12:15 6 9 15 27 33 37 <100 2.11E-10 As Read 27 12:30 6 9 15 27 33 37 (100 2.11E-10 As Read 27 12:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27 13:00 6 9 15 27 33 37 <100 2.11E-10 As Read 27 13:15 6 9 15 27 33 37 (100 2.11E-10 As Read 27 - 13:30 6 9 15 27 33 37 (100 2.11E-10 As Read 27 13:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27 14:00 6 9 15 27 33 37 <100 2.11E-10 As Read 27 14:15 6 9 15 27 33 37 (100 2.11E-10 As Read 27 14:30 6 9 15 27 33 37 <100 2.11E-10 As Read 27 14:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27 15:00 6 9 15 27 33 37 <100 2.11E-10 As Read 27 15:15 6 9 15 27 33 37 <100 2.11E-10 As Read 27 15:30 6 9 15 27 33 37 <100 2.11E-10 As Read 27 15:45 6 9 15 27 33 37 (100 2.11E-10 As Read 27 16:00 6 9 15 27 33 37 <100 2.11E-10 As Read 27 All count rates are net cpa. Allairsasolesassumea20cubicftvolume. i l i l 7/22/89,Page10.1.4.8
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, ANNUALEXERCZ5E, Revision 0 1
ELECTRICAL TUNNEL iA) TRAIN PLAN AT EL. 0' - 0" A: l B l C- ALL ALL ALL l ALL Time Dose Rate Snear Airborne Iodine Part. mR/hr l tR/hr l mR/hr - con uCi/cc cpa j cps 8:00 <1 <1 (1 (100 1.28E-10 As Read 16 3:00 (1 '1
< ,1
( <100 1.28E-10 As Read 16 10:00 <1 (1 (1 - -(100 1.28E-10 As Read 16 - - 10:30 <1 . <1 <1 (100 1.28E-10 As Read 16 10:45 <1 <1 <1 <100 1.28E-10 As lead 16 11:00 <1 - <1 <1 (100 1.28E-10 As Read 16 11:15 <1 <1 (1 - (100 1.28E-10 As Read 16 11:30 - <1 <1 <1 (100 1.28E-10 As Read 16 11:45 <1 <1 - <1 (100 1.28E-10 As Read 16 12:00 (1 (1 <1 <100 1.28E-10 As Read 16 12:15 <1 (1 (1 <100 1.28E-10 As Read 16 12:30 <1 (1 <1 <100' 1.28E-10 As Read 16 12:45 <1 <1 <1 <100 1.28E-10 As Read 16 13:00 <1 (1 (1 <100 1.28E-10 As Read 16 13:15 <1 (1 (1 (100 1.28E-10 As Read 16 13:30 <1- <1 <1 <100 1.28E-10 As Read 16 13:45 <1 <1 (1 (100 - 1.28E-10 As Read 16 14:00 (1 (1 (1 <100 -- 1.28E-10 As Read 16 l 14:15 <1 (1 <1 <100 1.28E-10 As Read 16 14:30 (1 - (1 <1 (100 1.28E-10 As Read 16 14:45 <1 <1 (1 (100 1.28E-10 As Read 16 15:00 <1 <1 <1 <100 1.28E-10 As Read 16 15:15 (1 <1 (1 <100 1.28E-10 As Read 16 1 15:30 <1 <1 <1 <100 1.28E-10 As Read 16 I 15:45 <1 (1 (1 (100 1.28E-10 As Read 16 l 16:00 <1 <1 (1 <100 1.28E-10 As Read 16 All count rates are net cpa. All air samples assume a 20 cubic ft volume. l l l j l \ l 1 7/22/89,Page10.1.4.9 i
y-~_-,.-__ . _ _ , _ _ ELECTRICAL TUNNEL (B) TRAIN PLAN AT EL. (-) 26' - 0" e tus W 4 g N c U U g e a r j 4 n n = j 1 u c ; N s 4 e ee - e O e** 10.].4.10
,t t ANNULLEXERC8SE, Revision 0 ELECTRICAL TCNNEL fB1 TRAIN PLAN AT EL. - 26' - 0" A l B l C ALL ALL ALL l ALL
-Time Dose Rate Saear Airborne Iodine Part.
mR/hr l mR/tr l mR/hr - cpa uCi/cc cpa l cpa 8:00 <1 <1 (1 (100 3.21E-10 As lead 40
'9:00 <1 <1 ,1
< <100 3.21E-10 As lead 40 10:00 <1 <1 (1 (100 3.21E-10 As Read 40 '
10:30 (1 . <1 (1 (100 3.21E-10 As Read 40 10:45 <1 <1 <1 <100 3.21E-10 As Read 40 11:00 <1 (1 <1 (100 3.21E-10 As Read 40 11:15 <1 (1 (1 <100 3.21E-10 As Read 40 11:30 <1 <1 <1 ( 100 3.21E-10 As Read 40 11:45 <1 <1 (1 (100 3.21E-10 As lead 40 12:00 <1 <1 (1 <100 3.21E-10 As Read 40 12:15 cl <1 <1 <100 3.21E-10 As Read 40 12:30 <1 (1 (1 - (100 3.21E-10 As Read 40 12:45 <1 <1 (1 (100 3.21E-10 As Read 40 13:00 <1 <1 (1 <100 3.21E-10 As Read 40 13:15 <1 (1 (1 <100 3.21E-10 As Read 40 13:30 <1 <1 (i <100 3.21E-10 As Read 40 13:45 <1 <1 <1 (100 3.21E-10 As Read 40 14:00 <1 <1. <1 (100 3.21E-10 As Read 40 14:15 <1 (1 <1 (100 3.21E-10 As Read 40 14:30 <1 <1 <1 (100 3.21E-10 As Read 40 14:45 <1 <1 <1 (100 3.21E-10 As Read 40 15:00 <1 !<1 <1 (100 3.21E-10 As lead 40 15:15 <1 (1 <1 <100 3.21E-10 As Read 40 15:30 <1 <1 <1 <100 3.21E-10 As Read 40 15:45 <1 (1 <1 (100 3.21E-10 As Read 40 16:00 <1- <1 <1 <100 3.21E-10 As lead 40 Allcountratesarenetcpa. Allairsamplesassumea20cubicftvolume. 7/22/89,Page10.1.4.10
h-
- i . WEST FEEDWATER PIPE CHASE PLAN AT EL. 3' - 0" :
1 G i l N ' f ' a at sist (t) D N tt s4 1 (2) m C Il e l I l 10.1.4.11 I
1 m. N g ANilUALEIERCISE; Revision 0 < WEST FEEDWATER PIPE CHASE PLAN AT IL. 3' - 0" A~ l B l'C- ALL ALL -ALL l ALL Time Dose Rate Snear Airborne Iodine Part. U mR/br j'mR/hr l mR/br - cpa UCi/cc' cpu . l cps - fg 8:00 <1 <1 '<1. <100 3.01E-10 As Read 38 9:00 (1- -<1. (
,1 - <100 3.01E-10 As Read 38 10:00 <1 <1 <1 (100. 3.01E-10 'As Read 38 4
10:30 ,
<1 . .1( <1 (100 '3.01E-10 As Read 38 10:45 <1 <1 ~(1 <100 3.01E-10 As Read 38 -
11:00 <1 <1 '(1 <100' 3.01E-10 As Read 38 11:15 <1 <1 <1 <100 3.01E-10 As Read 38 r 11:30 <1 <1 <1 <100 3.01E-10 As Read 38 11:45 <1 <1 <1 - (100 3.01E-10 As Read 38 12:00 <1 <1- - (1 <100 3.01E-10 As Read 38 12:15 <1 <1~ (1 <100 3.01E-10 As Read 38 12:30 .<1 <1 <1 - <100 3.01E-10 As Read 38 12:45 (l' <1 <1. (100 3.01E-10 As Read 38 13:00 .<1 <1 <1. (100 3.01E-10 As Read 38 13:15 (l ' <1 (1 <100 - 3.01E-10 As Read 38-13:30 <1 - <1- <1 (100 3.01E-10 As Read '38 13:45 '(1 (1 (1 '<100 3.01E-10 As Read 38 14:00 <1 (1 <1' <100 3.01E-10 -As Read 38 14:15 <1 <1 <1 (100 3.01E-10 As Read 38 14:30 <1 . (1 - <1 (100 3.01E-10 As Read 38 14:45 <1 <1. <1 <100- 3.01E-10 As Read 38 15:00 <1 (l ' <1 1<100 3.01E-10 As Read :38 15:15 <1 (1 <1 <100' 3.01E-10 As Read 38 15:30 .1
< (1 <1 <100- 3.01E-10 As Read 38 15:45 <1 <1 <1 <100 3.01E-10 As Reed 38 16:00 <1 1 <1 ' <100 3.01E-10 As Read 38 Allcount'ratesarenetcps.
All air samples assume a 20 cubic ft volume. p
+
7/22/89,Page10.1.4.11
h EAST FEEDWATER PIPE CHASE PLAN AT EL. 21 ' - 0 " , 27.' - 6 " l N h
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,. ANNUALEXERCISE,Revisioa0
+
EAST FEEDWATER PIPE CHASE AT EL. 21' ~ 0", 27' - 6" i A l B l C l, D l E l F ALL ALL Time Dose Rate l ALL- l alt. Dose Rate Smear Airborne Iodine Part. { mR/hr- l mR/hr l mR/hr l mR/hr j mR/hr l mR/br cpa l UCi/cc cps - l cps 8:00 N/A , N/A <1 (1- <1
<1 (100 4.81E-10 As Read 61 9:00 N/A . N/A ,1< .1( (1 (1 (100 4.81E-10 As Read '61 10:00 N/A. N/A (1 (1 '1
<1 < (100 4.81E-10 As lead 61 10:30 N/A . N/A <1 (1 <1 <1 <100 4.81E-10 As Read 61 10:45 N/A- N/A (1 (1
<1 (1 <100 4.81E-10 As Read 61 11:00 N/A N/A (1 <1 <1 (1 <100 4.81E-10 As Read 61 11:15 N/A N/A (1 (1 <1 <1 <100 4.81E-10 As Read 61 11:30 N/A N/A <1 <1 <1 (1 (100 4.81E-10 As Read 61 11:45 N/A N/A (l' <1 <1 (1 <100 4.81E-10 As Read 61 12:00 N/A N/A .<1 (1 <1 (1 <100 4.81E-10 As Read 61 12:15 N/A N/A <1 <1 <1 <1 <100 4.81E-10 As Read 61 12:30 N/A N/A <1 <1 <1 <1 <100 4.81E-10 As Read .61 12:15 N/A N/A <1 <1 <1 <1 (100 4.81E-10 As Read 61 13:00 N/A N/A <1 <1 <1 <1 (100 4.81E-10 As Read 61 13:15 N/A N/A <1. (1 <1 <1 <100 4.81E-10 As Read 61 13:30 N/A N/A <1- <1 (1 <1 (100. 4.81E-10 As Read 61 13:45 N/A N/A <1 (1 (1 <1 <100 4.81E-10 As Read 61 14:00 N/A N/A (1 (1 (1 (100
<1 4.81E-10 As Read 61 14:15 N/A N/A <1 <1 (1 (100
<1 4.81E-10 As Read 61 14:30 N/A N/A (1 <1 <1 <1 <100 4.81E-10 As lead 61 14:45 N/A N/A (1 (1 <1 <100
<1 4.81E-10 As Read 61 15:00 N/A N/A <1 <1 <1 <100
<1 4.81E-10 As Read 61 15:15 N/A N/A <1 <1 <1 (100
<1 4.81E-10 AsRead 61 15:30 N/A N/A <1 <1 <1 <100
<1 4.81E-10 As Read 61 15:45 N/A N/A (1 <1 <1 <100
<1 4.81E-10 As Read 61 16:00 N/A N/A (1 (1 (1 <100
<1 4.81E-10 As Read 61 All count rates are met cpa.
Allairsanelesassumea20cubicftvolute. 7/22/89,Page10.1.4.12
' EAST FEEDWATER PIPE CHASE ;
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1 ANEAL IIERCISE, hvision 0 ! EAST TEEIEATER FIPE CEASE PLAN AT EL. 3' - 0" ! A l B l C ALL ALL ALL l ALL Time Dose Rate Smear Airborne Iodine Part, tR/hr l tR/hr l tR/hr cpm UCi/cc cpa j cpm 8:00 <1 <1 (1 (100 4.81E-10 As Read 61 9:00 <1 <1 (1 (100 4.81E-10 As Read 61 10:00 <1 <1 '1
< (100 4.81E-10 As Read 61 10:30 (1 ,
<1 <1 <100 4.81E-10 As Read 61 10:45 <1 (1 <1 <100 4.81E-10 As Read 61 11:00 <1 <1 <1 (100 4.81E-10 As Read 61 11:15 <1 <1 (1 (100 4.81E-10 As Read 61 11:30 (1 (1 <1 (100 4.81E-10 As Read 61 11:45 <1 <1 <1 <100 4.81E-10 As Read 61 12:00 (1 (1 (1 <100 4.81E-10 As Read 61 12:15 <1 <1 <1 (100 4.81E-10 As Read 61 12:30 <1 <1 <1 (100 4.81E-10 As Read 61 12:45 <1 <1 (1 <100 4.81E-10 13 Read 61 13:00 <1 <1 <1 (100 4.81E-10 As Read 61 13:15 <1 <1 <1 <100 4.81E-10 As Read 61 13:30 <1 <1 <1 <100 4.81E-10 As Read 61 13:45 <1 '1
< <1 <100 4.81E-10 As Read 61 14:00 <1 <1 <1 <100 4.81E-10 As Read 61 14:15 <1 (1 <1 (100 4.81E-10 As Read 61 14:30 <1 (1 <1 <100 4.81E-10 As Read 61 14:45 <1 <1 <1 <100 4.81E-10 As Read 61 15:00 <1 (1 <1 <100 4.81E-10 is Read 61 15:15 <1 (1 <1 <100 4.81E-10 As Read 61 15:30 <1 <1 <1 (100 4.81E-10 As Read 61 15:45 <1 <1 <1 <100 4.81E-10 As Read 61 16:00 (1 (1 <1 <100 4.81E-10 As Read 61 All count rates are net cpa.
All air samples assume a 20 cubic ft volume. 7/22/89,Page10.1.4.13
o MAIN STEAM FEEDWATER PLAN AT EL. 28' J
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MAIN STEAM FEEDiiATER PU.N AT EL. 28'
, , A l B. l C l D l E { f ALL l ALL ALL ALL l
Time Dose Rate Dose Rate Seear Airborne Iodine Part. A tR/hr l mR/hr l mR/hr l mR/hr mR/hr l mR/hr cpa l UCi/cc cpa l cpa 8:00 <1. <1 (1 (1 <1 j <1 <100 '4.81E-10 As Read . 61 9:00 <1 (1 ,1( <1 <1 <1 <100 4.81E-10 As Read 61 10:00 <1 (1 <1 (1 (1 (1
<100 4.81E-10 AsRead 61 10:30 (1 . (1 <1 <1 (1 ' (1 <100 4.81E-10 As Read 61 1 10:45 <1 - '1
< (1 (1 <1 (1 (100 4.81E-10 As Read 61 {
11:00 <1 <1 <1 <1 (1 <1- <100 4.81E-10 AsRead 61 11:15 <1 <1 <1 <1 <1 ~ <1 <100 4.81E-10 As Read 61 11:30 <1 <1 - <1 (1 <1 <1 <100 4.81E-10 As Read 61-11:45 <1 <1 <1 <1 <1 <1 (100 4.81E-10 As Read 61 12:00 <1 (1 (1 <1 <1 (1 <100 4.81E-10 As Read 61' 12:15 <1 <1 (1 <1 <1 <1 (100 4.81E-10 AsRead 61 12:30 (1 <1 <1 <1 <1 <1 <100 4.81E-10 As Read 61 12:45 <1 (1 <1 <1 <1 <1 (100 4.81E-10 As Read 61 13:00 <1 <1 (1 <1 <1 <1 <100 4.81E-10 As Read 61 13:15 <1 <1 - <1 (1 (1 <1 (100 4.81E-10 As Read 61 13:30 (1 (1- - <1 <1 <1 (1 ' <100 4.81E-10 As Read 61 13:45 <1 (1 <1 (1 <1- <1 (100 4.81E-10 As Read 61 14:00 <1 <1 <1 <1 (1 <1 (100 4.81E-10 As Read 61 14:15 <1 <1 <1 <1 (1 (1 <100 4.81E-10 As Read 61 14:30 <1 <1 <1 <1 <1 <1 <100 4.81E-10 As Read 61 14:45 <1 (1 <1 <1 <1 (1 (100 4.81E-10 As Read 61 15:00 <1 (1 <1 <1 (1 <1 <100 4.81E-10 As Read 61 315:15 <1 <1 - <1 <1 <1 <1 (100 4.81E-10 As Read 61 15:30 <1 (1 (1 (1 <1 <1 (100 4.81E-10 As Read 61 15:45 <1 (1 <1 (1 <1 - <1 <100 4.81E-10 As Read 61 (1 <1 <1 <1 4.81E-10 16:00 <1 <1 <100 As Read 61 All count rates are net cpa. All air sarples assume a 20 cubic ft volume. l l l 7/22/89,Page10.1.4.14 l i
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.001UAL EXERCISE, Revision 0 l PAB PU.N AT EL. 7' - 0" i A l B l C l D l E l f ALL l ALL ALL l ALL fine Dose Rate Dose Rate Smear Airborne Iodine Part, tR/hr l tR/hr l tR/hr l d/hr mR/hr l mR/hr ept l uCi/cc cpn ! cpn 8:00 <1 8 82 <1 25 4 (100 3.85E-10 As Read 49 i 9:00 <1 8 ,82 <1 25 4 (100 3.85E-10 As Read 49 I 10:00 <1 8 82 <1 25 4 (100 3.85E-10 As Read 49 10:30 (1 . 8 82 <1 25 4 (100 3.85E-10 As Read 49 10:45 <1 8 82 <1 25 4 <100 3.85E-10 As Read 49 11:00 <1 8 75 (1 20 4 <100 3.85E-10 As Read 49 11:15 <1 8 70 <1 17 4 <100 3.85E-10 As Read 49 11:30 (1 8 60 <1 12 4 <100 3.85E-10 As Read 49
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11:45 <1 8 60 <1 12 4 (100 3.85E-10 As Read 49 i 12:00 <1 8 60 <1 12 4 <100 3.85E-10 As lead 49 12:15 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 12:30 <1 8 60 <1 12 4 (100 3.85E-10 As Read 49 12:45 <1 8 60 (1 12 4 <100 3.85E-10 As Read 49 13:00 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 13:15 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 13:30 (1 8 60 (1 12 4 <100 3.85E-10 As Read 49 13:45 <1 8 60 (1 12 4 <100 3.85E-10 As Read 49 14:00 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 14:15 <1 8 60 (1 12 4 <100 3.85E-10 As Read 49 14:30 <1 8 60 <1 12 4 (100 3.85E-10 As Read 49 14:45 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 15:00 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 15:15 <1 8 60 (1 12 4 (100 3.85E-10 As Read 49 15:30 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 15:45 <1 8 60 <1 12 4 (100 3.85E-10 As Read 49 16:00 <1 8 60 <1 12 4 <100 3.85E-10 As Read 49 All count rates are net cpa. All air samples assume a 20 cubic ft volume.
)
I 7/22/89, Page 10.1.4.15
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r I y, ,. A10EALEIERCISE, Revision 0 PAB PLAN AT EL. 2' - 0" & -) 6' - 0" A l B l C l D l E l T ALL ALL l ALL l ALL Time Dose Rate Dose Rate Shear Airborne Iodine Part. aR/hr. l mR/br l mR/hr l tR/hr mR/hr l mR/hr cps l UC1/cc cpa l cps 8:00 <1 <1 2 <1 10 55 (100 5.23E-10 As Read 66 9:00 <1 - <1 ,2 <1 10 55 <100 5.23E-10 .As Read - 66 10:00 (1 (1 2 <1 10 55 (100 5.23E-10 As Read 66 - 10:30 <1 ,
<1 2 <1 10 55 (100 5.23E-10 As Read 66 10:45 - <1 (1 2 <1 10- 55 <100 5.23E-10 As Read 66 11:00 <1 (1 2 <1 9 52 <100 5.23E-10 As Read 66 11:15 <1 <1 2 <1 8 50 <100 5.23E-10 As Read 66 L
11:30 4 <1 (1 2- <1 8 45 (100 5.23E-10 As Read ~ 66 11:45 <1 '<1 2 <1 8 45 (100 5.23E-10 As Read 66 l 12:00 - <1 '1
< 2 (1 8 45 (100 5.23E-10 As Read 66 12:15 <1 <1 2 <1 - 8 45 (100 5.23E-10 As Read 66 12:30 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 12:45 <1- <1 2 <1 8 45 (100 5.23E-10 As Read 66 13:00 <1 <1 2 <1 8 45 (100 5.23E-10 As Read 66 13:15 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 13:30 <1 (1 2' <1 8 45 s100 5.23E-10 As Read 66 13:45 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 14:00 <1 <1 '2 <1 8 45 (100 5.23E-10 As Read '66 14:15 <1~ (1 2 <1 8 45 <100 5.23E-10 As Read 66 14:30 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 14:45 <1 <1 - 2 <1 8 45 <100 5.23E-10 As Read 66 15:00 (1 (1 2 <1 8 45 <100 5.23E-10 As Read 66 15:15 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 15:30 <1 <1 2 <1 8 45 (100 5.23E-10 As lead 66 15:45 <1 <1 2 (1 8 45 <100 5.23E-10 As Read 66 16:00 <1 <1 2 <1 8 45 <100 5.23E-10 As Read 66 All count rates are net cpa.
All air samples assume a 20 cubic ft volume. 7/22/89,Page10.1.4.16 l
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arthr l mR/hr l mR/tr l mR/hr mR/hr l mR/hr CDs l uCi/cc cpu l cps , i 8:00 <1- <1- 2 2 2 .2 <100 4.48E-10 As Read 56 I 9:00 (1- <1 .2 2 2 2 ' <100 4.48E-10 As Read 56 10:00 <1 <1 2 2 2 2 (100 4.48E-10 As Read 56 10:30 :<1 <1- 2 2 2 2 .<100 4.48E-10 As Read 56 l 10:45 <1 (1 2 2 2 2 -(100 4.48E-10 As Read 56 11:00 . <1 <1. 2 2 2 2 (100 4.48E-10 As Read 56 ; 11:15 (1 <1- 2 2 2 2 (100 4.48E-10 As Read 56 11:30 <1 <1 2 2 2 2 (100 4.48E-10 As Read 56 11:45 (1 (1 2 2 2 2 (100 4.48E-10 As Read- 56 12:00 <1 <1" 2 2. 2 2 -(100 4.48E-10 As Read 56 12:15 <1 <1 2 2 2 2 <100 4.48E-10 As Read 56' 12:30 (1 <1 2 -2 2 2 <100 4.48E-10 As Read 56 12:45 <1 (1 2- 2 2 -2 <100 4.48E-10 As Read 56 13:00 (1 (1. 2 2 2 2 . <100- 4.48E-10 As Read 56-13:15 <1 (1 2 2 2 2 <100 4.48E-10 As Read 56 13:30 <11 (1 2 2 2 2 -(100 4.48E-10 As Read 56 13:45 <1. <1 2 2 2 2 <100 4.48E-10 As Read 56 14:00 -<1 <1- 2 2 2 2 (100- 4.48E-10 As Read 56 14:15 .1 < -<1 2 2 2 2 <100 4.48E-10 -As Read 56 14:30 <1 <1 2 2 2 2 <100 4.48E-10 As Read 56 14:45 .1 < (1 2 2 2 2 <100 4.48E-10 As Read 56 15:00 <1 -<1- 2 2 2 2 (100 4.48E-10 As Read 56 15:15 <1 <1 2 2 2 2- <100 4.48E-10 As Read 56 15:30 <1 .1- < 2 2 2 2 (100 4.48E-10 As Read 56 15:45 - <1 <1 2 2 2 2 (100 4.48E-10 As Read 56 16:00 <1 (1 2 2 2 2 <100 4.48E-10 As Read 56 All count rates are net cps. All air samples assume a 20 cubic ft volume. 7/22/89,Page10.1.4.17 ! 1 1 -- - _ - - _ _ _ _ _ - - _ -_ - -__ D
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ANNUALEIIRCZSI, Revision 0 0 PAB PU.N AI EL. 25' - 0" ! A l B l C l D l E l F ALL l ALL ALL l ALL Tine Dose Rate Dose Rate Smear Airborne Iodine Part. tR/hr l mR/hr j mR/hr l tR/hr l mR/hr l mR/hr cpa l uCi/cc com l cps I 8:00 <1 <1 <1 <1 <1 <1 <100 1.30E-10 As Read 16 9:00 (1 <1 <1 <1 <1 (1 <100 1.30E-10 As Read 16 10:00 'l <1 ~<1 (1 <1 <1 <100 1.30E-10 As Read 16 10:30 <1 (1 <1 <1 <1 <1 <100 1.30E-10 As Read 16
~ l 10:45 <1 (1 (1 (1 <1 (1 (100 1.30E-10 As Read 16 l 11:00 <1 <1 (1 (1 <1 (1 <100 1.30E-10 As Read 16 11:15 <1 <1 (1 (1 <1 (1 (103 1.30E-10 As Read 16 11:30 (1 <1 <1 <1 <1 (1 <100 1.30E-10 As Read 16 11:45 <1 <1 <1 <1 <1 <1 <100 1.30E-10 As Read 16 12:00 <1 <1 (1 <1 <1 <1 <100 1.30E-10 As Read 16 12:15 <1 <1 (1 <1 <1 <1 (100 1.30E-10 As Read 16 12:30 <1 (1 <1 <1 <1 <1 <100 1.30E-10 As Read 16 12:45 <1 <1 <1 <1 <1 (1 (100 1.30E-10 As Read 16 13:00 <1 (1 (1 <1 <1 <1 <100 1.30E-10 As Read 16 13:15 <1 <1 (1 <1 <1 <1 <100 1.30E-10 As Read 16 13:30 <1 <1 <1 (1 <1 <1 <100 1.30E-10 As Read 16 13:45 <1 <1 <1 <1 <1 <1 <100 1.30E-10 As Read 16 14:00 (1 <1 (1 <1 <1 <1 <100 1.30E-10 As Read 16 14:15 <1 <1 (1 <1 <1 <1 (100 1.30E-10 As Read 16 14:30 <1 <1 (1 <1 <1 <1 <100 1.30E-10 As Read 16 14:45 <1 <1 <1 (1 <1 <1 (100 1.30E-10 As Read 16 15:00 (1 (1 (1 <1 <1 <1 (100 1.30E-10 As Read 16 15:15 <1 <1 <1 (1 <1 <1 (100 1.30E-10 As Read 16 15:30 <1 <1 <1 (1 <1 <1 (100 1.30E-10 As Read 16 15:45 (1 (1 <1 <1 <1 <1 <100 1.30E-10 As Read 16 16:00 <1 <1 <1 (1 <1 <1 (100 1.30E-10 As Read 16 All count rates are net cp.
1Allairsanolesassuea20cubicftvolue. I 7/22/89,Page10.1.4.18
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L A!0 GAL EIERCISE, Revision 0 f PIB P'M AI EL. 53' - 0" A l B l C D l l E l T ALL l ALL ALL l ALL Time Dose Rate Dose Rate Smear Airborne Iodine Part, tR/hr l mR/hr l tR/hr l ER/hr mR/hr'l mR/hr cpt l UCi/cc com l cpm 8:00 <1 <1 <1 (1 3 <1 <100 1.15E-10 As Read 14 9:00 <1 <1 (1 <1 3 <1 (100 1.15E-10 As Read 14 10:00 <1 <1 '1 < <1 3 <1 <100 1.15E-10 As Read 14 10:30 <1 <1 <1 (1 3 <1
<100 1.15E-10 As Read 14 10:45 <1 <1 <1 (1 3 <1 (100 1.15E-10 As Reai 14 11:00 (1 <1 - (1 (1 3 <1 (100 1.15E-10 As Read 14 11:15 <1 <1 <1 <1 3 (1 <100 1.15E-10 As Read 14 11:30 <1 <1 <1 <1 3 <1 <100 1.15E-10 As Read 14 11:45 <1 <1 <1 <1 3 <1 (100 1.15E-10 As Read 14 12:00 <1 (1 (1 <1 3 <1 <100 1.15E-10 As Read 14 12:15 <1 (1 (1 (1 3 <1 <100 1.15E-10 As Read 14 12:30 (1 <1 <1 .1( 3 <1 (100 1.15E-10 As Read 14 12:45 <1 (1 (1 <1 3 <1 (100 1.15E-10 As Read 14 13:00 <1 <1 (1 <1 3 <1 (100 1.15E-10 As Read 14 13:15 <1 <1 <1 (1 3 <1 <100 1.15E-10 As Read 14 13:30 <1 <1 <1 <1 3 <1 <100 1.15E-10 As Read 14 13:45 <1 <1 <1 <1 3 :1 <100 1.15E-10 As Read 14 14:00 <1 <1 (1 (1 3 <1 (100 1.15E-10 As Read 14 14:15 <1 (1 (1 (1 2 <1 (100 1.15E-10 As Read 14 14:30 <1 <1 <1 <1 2 <1 (100 1.15E-10 As Read 14 14:45 <1 <1 <1 <1 2 <1 (100 1.15E-10 As Read 14 15:00 <1 <1 <1 <1 2 <1 <100 1.15E-10 As Read 14 15:15 <1 <1 <1 (1 2 <1 <100 1.15E-10 As Read 14 15:30 (1 (1 (1 (1 2 <1 <100 1.15E-10 As Read 14 15:45 <1 <1 (1 <1 1 (1 (100 1.15E-10 As Read 14 7/22/89,Page10.1.4.19
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.8:00 <1 <1 <1 <1 (1 <1 (1 <1 (100 1.05E-10 As Read 13 9:00 (1 <1 (1 <1 (1 <1 (1 <1 (100 1.05E-10 'As Read ' 13 10:00 <1 (1 <1 il <1 <1 <1 (1, (100 1.05E-10 As Read 13 10:30 <1 <1 <1 <1 <1 . <1 <1 <1 <100 1.0$E-10 As Read 13 10:45 <1 (1 <1 <1 (1 <1 <1 (1 (100 1.05E-10 As Read 13 11:00 <1 (1 <1 <1 <1 <1 <1 <1 <100 1.05E-10 As Read 13 11il5 <1 (1 (1 (1 <1 (1 <1 <1 (100 1.05E-10 As Read 13 11:30 <1 (1- <1 <1 <1 (1 <1 <1 (100 1.05E-10 As Read 13 11:45 <1. ' (1 (1 <1 <1 '1< <1 <1 (100 1.05E-10 As Read 13 12:00 (1 <1 <1' (1 (1 <1 .1
< <1 <100 1.05E-10 As Read 13 12:15 <1 <1 <1 <1 <1 <1 (1 <1 <100 1.05E-10 As Read 13 12:30 (1 <1 (1 <1 (1 <1 <1 <1 (100 1.05E-10 As lead 13 12:45 (1 .~<1 (1 <1 (1 <1 <1 (1 <100 1.05E-10 As Read 13 13:00 <1 <1 <1 <1 <1 <1 <1 (1 (100 1.05E-10 As Read 13 13:15 <1. <1 <1- <1 (1 <1 <1 (1 (100 1.05E-10 As Read 13 13:30 <1 <1 <1 <1 <1 <1 <1 <1 (100 1.05E-10 As Read 13 13:45 <1. (1 <1 (1 <1 <1 <1 <1 (100 1.05E-10 As lead 13 14:00 <1 <1 <1 <1 (1 <1 (1 <1 (100 1.05E-10 As Read 13
.4:15 <1 <1 ~ <1 <1- <1 <1 (1 (1 <100 1.05E-10 As Read 13 14:30 <1 <1 <1 <1 (1 (1 <1 <1 (100 1.05E-10 As Read 13 14:45 <1 <1 <1 <1 (1 <1 <1 (1 <100 1.05E-10 As Read 13 15:00 (1 (1 <1 (1 <1 (1 <1 (1 (100 1.05E-10 As Read 13 15:15 <1 (1 <1 <1 <1 <1 <1 <1 (100 1.05E-10 As Read 13 15:30 <1 <1 <1 <1 <1 <1 <1 <1 (100 1.05E-10 As Read 13 15:45 .1 < <1. <1 (1 <1 <1 <1 <1 <100 1.05E-10 As Read 13.
16:00 <1 (1 <1 <1 (1 <1 - <1 <1 <100 1.05E-10 As Read 13 Allcountratesarenetcpa. Allairsamplesassumea20cubicftvolume.
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1 7/22/89,Page10.1.4.20
- s. 1 F
G i NEW HAMPSHIRE YANKEE i SEABROOK STATION i l 1989 GRADED EXERCISE
~
l l 10.1 INPL ANT DAT A 10.1.5 CHEMISTRY SAMPLE DOSE RATES { l k l l i i 4 _ _ _ _ _ _ _ . _ _ - - - - - - - - - - - _ - - - - - . - - - ^ - - ~ ~ - ~ ' ~ ~ ^ ~~^ ^~~
ANNUAL EXERCISE, Revision 1.0 l I 4 Containment Sump Sample 1 Sample Sample mR/hr mR/hr mR/hr Time' Media Contact 1 ft 3 ft SAMPLE NOT OBTAINED IN THIS SCENARIO NOTE: Each 10 ml PASS Liquid Sample Syringe (Diluted 481:1) I Containment Atmosphere Sample Sample mR/hr mR/hr mR/hr Time Media Contact 1 ft 3 ft 8:00 Gas As Read As Read- As Read 9:00 Gas As Read As Read As Read 10:00 Gas As Read As Read As Read 11:00 Gas As Read As Read As Read 12:00 Gas As Read As Read As Read 13:00 Gas As Read As Read As Read 14:00 Gas As Read As Read As Read 15:00 Gas As Read As Read As Read 16:00 Gas As Read As Read As Read NOTE: 75 ml Gas Sample l 9/20/89, Page 10.1.5.1
? i ANNUAL EXERCISE, Revision 1.0 WRGM Particulate and Icdine Samples Sample Sample mR/hr mR/hr mR/hr
. Time Media Contact 1 ft 3 ft 8:00 Charcoal As Read As Read As Read Filter As Read As Read As Read -
9:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 10:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 11:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 12:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 13:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 14:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 15:00 Charcoal As Read As Read As Read Filter As Read As Read As Read 16:00 Charcoal As Read As Read As Read Filter As Read As Read As Read NOTE: 60 Minute Sample 0 0.06 scfm 9/20/89, Page 10.1.5.2
s ANNUAL EXERCISE, Revision 1.0 Reactor Coolant Liquid Sample (Routine) Sample. Sample mR/hr mR/hr mR/hr Time Media Contact i ft 3 ft 8:00 Liquid 20 10 1 9:00 Liquid 20 10 1 10:00 Liquid 19 9 1 11:00 Liquid 15 7 1 12:00 Liquid 12 5 1 13:00 Liquid 10 4 As Read 14:00 Liquid 9 3 As Read 15:00 Liquid 8 1 As Read 16:00 Liquid 8 1 As Read Note : 1000 ml sample volume. Reactor Coolant Liquid Sample (PASS) Sample Sample mR/hr mR/hr mR/hr i Time Media Contact 1 ft 3 ft 8:00 Liquid As Read As Read As Read 9:00 Liquid As Read As Read As Read 10:00 Liquid As Read As Read As Read 11:00 Liquid As Read As Read As Read 12:00 Liquid As Read As Read As Read 13:00 Liquid As Read As Read As Read 14:00 Liquid As Read As Read As Read 15:00 Liquid As Read As Read As Read 16:00 Liquid As Read As Read As Read NOTE: Each 10 ml PASS Liquid Sample Syringe (Diluted 481:1)
~
Reactor Coolant System Gas (PASS) ; Sample Time Sample Media mR/hr mR/hr 1 ft mR/hr 3 ft l Contact 8:00 Gas 0.1 As Read As Read 9:00 Gas 0.1 As Read As Read 10:00 Gas As Read As Read As Read 11:00 Gas As Read As Read As Read 12:00 Gas As Read As Read As Read 13:00 Gas As Read As Read As Read 14:00 Gas As Read As Read As Read 15:00 Gas As Read As Read As Read 16:00 Gas As Read As Read As Read i NOTE: Each 1 ml PASS Gas Sample Syringe i l l l 9/20/89, Page 10.1.5.3
h . (~ l l 4 NEW HAMPSHIRE YANKEE 1 SEABROOK STATION l b 1989 GRADED EXERCISE l' 10,1 I. N PL'A NT D AT A 10.1.6 HEALTH PHYSICS AIR SAMPLE ANALYSES
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.t, NEW HAMPSHIRE YANKEE SEABROOK STATION 1989. GRADED. EXERCISE -
10.1. INPL ANT ' D A'T A 10.1.6 HEALTH PHYSICS AIR' SAMPLE ANALYSES 4 NOTE TO CONTROLLER
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AIR SAMPLE DATA IS VALID DURING AND AFTER PASS AND HYDROGEN S AMPLING. l =:-- . _. .__ . _ _ _ _ _ _ _ _ - _
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. . ANNUAL EXERCISE, Revision 0
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. ,1 l NEW HAMSHIRE YANKEE HEALTH PHYSICS DEPARTMENT l-SAMPLE DESCRIPTION: E. .FW PIPE CHASE (During H Sampling)
GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 20 CUBIC FEET DATA COLLECTED ON: 9/27/89 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 1.55E-10 1.69E-12 1.53E-10 1.69E-12 CS-134 1.60E-10 1.68E-12 1.58E-10 1.68E-12 CS-137 1.63E-10 2.02E-12 1.61E-10 2.02E-12 TOTAL 4.78E-10 5.39E-12 4.72E-10 5.39E-12 g I I i 1 l 7/22/89, Page 10.1.6.1
. ANNUAL EXERCISE,.Revisio[1 O
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f r.! CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE HEALTH PHYSICS DEPARTMENT SAMPLE DESCRIPTION: PAB El. 25' (During PASS Sampling) j GEOMETRY DESCRIPTION: FACE LOADED ' SAMPLE SIZE: 20 CUBIC FEET DATA COLLECTED ON: 9/27/89 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 3.30E-11 5.86E-13 3.24E-11 5.86E-13 CS-134 3.40E-11 6.79E-13 3.33E-11 6.79E-13^ CS-137 3.47E-11 4.45E-13 3.42E-11 4.45E-13 TOTAL 1.02E-10 1.71E-12 9.99E-11 1.71E-12 7/22/89, Page 10.1.6.2
NEW HAMPSHIRE YANKEE SEABROOK STATION
~
1989 GRADED EXERCISE - TABLE OF CONTENTS 10.2 CHEMISTAY D ATA l I
_ _ = . _ - _ _ _ _ _ _ - . l-l NEW HAMPSHIRE YANKEE-SEABROOK STATION ; 1 1989 GRADED EXERCISE . i 1 TABLE OF CONTENTS l 10.2 CHEMIST AY D AT A 10.2.1 RCS DAT A'(CHEMICAL ANALYSES) 10.2.1.1 PRIMARY CHEMISTRY REPORT 10.2.1.2 RCS CHEMISTRY DATA
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1989 GRADED EXERCISE 10.2 CHEMISTRY D AT A 10.2.1 RCS DATA (CHEMICAL ANALYSES) 10.2.1.1 PRIMARY CHEMISTRY REPORT' (
i
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ANNUAL EXERCISE, Revision 1.0 UNIT: 1 DATE: 9/27/89 TIME: 05:30 UNIT STATUS: Mode 1 @ 100% REACTOR COOLANT Technical Specification Requirements Limits Parameter Units Steady Transient Results Chlorides ppm <0.15 <1.5 <0.01 Fluoride ppm <0.15 <l.5 <0.01 Oxygen ppm <0.10 <l.0 <0.005 Boron ppm ---- ---- 102 100/E: 55.6 4Ci/gm Date Calculated: 9/22/89 _ Parameter Limit Units Results Gross Activity 100/E gCi/gm 2.15E-03 Dose Equiva-lent Iodine 1.0 uCi/gm 7.94E-05 Operation Guidelines Parameter Units Control Range Results Hydrogen cc/kg 25 - 50 31 Lithium ppm 0.7 - 2.2 0.9 Remarks: 1 Copy: Chemistry File Technician: C. H. Tech Reactor Engineering CH / HP Manager HP Operations Supv. 9/19/89, Page 10.2.1.1
L ... i i j NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 10.2 CHEMISTRY D ATA 10.2.1 RCS DATA (CHEMICAL ANALYSES) 10.2.1.2- RCS CHEMISTRY DATA L. l 1
ANNUAL EXERCISE, Revision 1.0 i i Boron. Lithium Chloride Fluoride Oxygen Hydrogen % H2 Co nc '. -Conc. Conc. Conc. Conc. Conc. In- k Time- ppm ppm ppm ppm ppm cc/kg Cont. 8:00 102 -0.9 <0.01 <0.01 <0.005 31 0 8:15 102 0.9 <0.01 <0.01 <0.005 31 0 8:30 102 0.9 <0.01 <0.01 <0.005 31 0 8:45 102 0.9 <0.01 <0.01 <0.005 31 0 9:00 102 0.9 <0.01 <0.01 <0.005 31 0 9:15 102 0.9 <0.01 <0.01 <0.005 31 0 9:30 102 0.9 <0.01 <0.01 <0.005 31 0 9:45 102 0.9 <0.01 <0.01 <0.005 31 0 10:00 102 0.9 <0.01 <0.01 <0.005 31 0 10:15 102 0.9 <0.01 <0.01 <0.005 31 0 10:30 102 0.9 <0.01 <0.01 <0.005 31 0 10:45 102 0.9 <0.01 <0.01 <0.005 31 0 11:00 102 0.9 <0.01 40.01 <0.005 31 0 11:15 129 0.2 <0.01 .<0.01 0.005 23 0 11:30 259 0.1 <0.01 <0.01 0.008 17 0 11:45 388 <0.1 <0.01 <0.01 0.5 9 0 12:00 518 <0.1 <0.01 <0.01 0.75 6 0 12:15 647 <0.1 <0.01 <0.01 2 2 0 12.30 777 <0.1 <0.01 <0.01 7 <1 0 12 : ?. 5 906 <0.1 <0.01 <0.01 7 <1 0 13:00 1036 <0.1 <0.01 <0.01 7 <1 0 13:15 1165 <0.1 <0.01 <0.01 7 <1 0 13:30 1294 <0.1 <0.01 <0.01 7 <1 0 1 13:45 1424 <0.1 <0.01 <0.01 7 <1 0 14:00 1553 <0.1 <0.01 <0.01 7 <1 0 14:15 1683 <0.1 <0.01 <0.01 7 <1 0 14:30 1812 <0.1 <0.01 <0.01 7 <1 0 14:45 1942 <0.1 <0.01 <0.01 7 <1 0 15:00 2071 <0.1 <0.01 <0.01 7 <1 0 15:15 2200 <0.1 <0.01 <0.01 7 <1 0 15:30 2200 <0.1 <0.01 <0.01 7 <1 0 15:45 2200 <0.1 <0.01 <0.01 7 <1 0 16:00 2200 <0.1 <0.01 <0.01 7 <1 0
- 1. Analysis are given for the time sample is taken. Controller must note time sample is taken and use data wher, analysis is complete.
i i 9/19/89, Page 10.2.1.2 !
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1989 GRADED EXERCISE 10.2 CHEMISTAY D AT A 10.2.2 GAMMA SPECTROSCOPY ANAYLSES 10.2.2.1 REACTOR COOLANT SYSTEM 10.2.2.2 CONT AINMENT ATMOSPHERE 10.2.2.3 WRGM FILTERS
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, 10.2 CHEMISTRY D AT A
- 10.2.2 GAMM A- SPECTROSCOPY ANAYLSES -
,-o 10.2.2.1 REACTOR COOLANT SYSTEM t r- NOTE TO CONTROLLER IN)T1 AL SAMPLE RESULTS -ARE VALID UNTIL i 100 AM 1 1 _____ - _ - - - - - - - - - - - - - - - - - - - . - _ - - -. . - - - - - - 1
I y _ ANNUAL EXERCISE,. Revision 2.0^
l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE-NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS L GEOMETRY' DESCRIPTION: TOP SHELF SAMPLE SIZE: ' GAS. VIAL DATE. COLLECTED ON: 9/27/89 AT 0700 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE~ iMEASURED ERROR CORRECTED ERROR Kr-85m 1.17E-04 1.20E-06' 1.19E-04 1.20E-06 Kr-85 .2.95E-06 3.16E-08 2.98E-06 3.16E-08
.Kr-87 2.26E-04 2.31E-06 2.28E-04 2.31E-06 F Kr-88 3.18E-04 3.21E-06' 3.21E-04 3.21E-06 Xe-131m'- 4.45E-06 4.78E-08 4.50E-06 4.78E-08 Xe-133m 2.82E-05 2.82E-07 2.84E-05 2.82E-07 Xe-133 8.99E-04 9.11E-06 9.08E-04 9.11E-06 Xe-135 1.75E-04 1.84E-06 1.76E-04 1.84E-06 TOTAL 1.77E-03 1.80E-05 1.79E-03 1.80E-05i l
I l l 9/20/89, Page 10.2.2.1.1
o y 9 '
- . ANNUAL EXERCISE, Ravision 2.0 C
GAMMA SPECTRUM ANALYSIS [ n CANBERRA SPECTRAN-F-V3.00 SOFTWARE NEW'HAMSHIRE YANKEE CHEMISTRY DEPARTMENT L SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE
, LGEOMETRY: DESCRIPTION: TOP SHELF
- SAMPLE. SIZE: 10.0 CC VIAL
!! DATE COLLECTED ON: 9/27/89 AT 0700 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131- 4.41E-05 4.61E-07 4.45E-05 4.61E-07 I-132 6.39E-05 6.71E-07 6.45E-05 6.71E I-133 9.01E-05 9.05E-07 9.10E-05 9.05E-07 I-134 9.87E-05 l'.04E-06 9.97E-05 1.04E-06 I-135 8.41E-05 8.89E-07 8.50E-05 8.89E-07 Cs-134 4.09E-08 4.42E-10 4.13E-08 4.42E-101 Cs-137 2.04E-08 2.17E-10 2.06E-08 2.17E-10' Mn-54 1.16E-08 1.20E-10 1.17E-08 1.20E-10.
Co-60 6.28E-08 6.38E-10 6.34L-08 6.38E-10 Co-58 4.88E-08 5.13E-10 4.93E-08 5.13E-10. Fe-59 5.78E-08 6.19E-10 5.85E-08 6.19E-10: TOTAL 3.81E-04 3.97E-06 3.85E-04 3.97E-06 DE-131 5.95E-05 6.42E-07 6.02E-05 6.42E-07 NOTE: Results shown above are corrected for any dilution. k 9/20/89, Page 10.2.2.1.1 - 2
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' SAMPLE ' DESCRIPT7, ON:-' RCS- GAS GEOMETRY . DESCR11 TION: TOP' SHELF SAMPLE SIZE:' GAS: VIAL
-DATE. COLLECTED'ON: 9/27/89 AT 1100
'. - RADIONUCLIDES'~A'NALYSIS REPORT
- i. ACTIVITY CONCENTRATION'IN uCi/cc NUCLIDE. MEASURED ERROR CORRECTED ERROR.
'Kr-85m 2.82E-05 5.67E-06 3.39E-05 5.67E-06 Kr-85: ~7.36E-07 1.48E-07 8.84E-07 1'.48E-07 Kr-87 4.92E-05 9.85E-06 5.91E-05 9.85E ~ Kr-8 8 : 7.48E-05 1.50E-05. 8.98E-05 1.50E-05
'Xe-131m 1.11E-06 2.23E-07. 1.33E-06' .2.23E Xe-1333- 7.02E-06 1.41E-06 8.43E-06 1.41E-06i.
Xe-133 2.24E-04 4.50E-05 2.69E-04 '4.50E-051 i Xe-135' 4.2BE-05 8.60E-06 5.14E-05 8.60E-06i~ TOTAL 4.28E-04 8.59E-05' 5.14E-04 8.59E-05l 1: I :t.- i i I l l 9/20/89, Page 10.2.2.1.2 ; , i __._- _____m._ _ _ _ _ m____.m___.___________m___ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ . - _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _
i ANNUAL EXERCISE, Revision 2.0 n. I GAMMA SPECTRUM ANALYSIS i i CANBERRA SPECTRAN-F V3.00 SOFTWARE . NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1100 RADIONUCLIDES ANALYSIS REPORT l ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131. 4.40E-05 8.81E-06 5.28E-05 8.81E-06 I-132 5.92E-05 1.18E-05 7.11E-05 1.18E-05 I-133 8.93E-05 1.79E-05 1.07E-04 1.79E-05 I-134 8.10E-05 1.62E-05 9.72E-05 1.62E-05 I-135 8.19E-05 1.64E-05 9.83E-05 1.64E-05 Cs-134 4.08E-08 8.17E-09 4.90E-08 8.17 E-09: Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E Mn-54 1.16E-09 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.81E-09 5.86E-08 9.81E-09 Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08 TOTAL 3.56E-04 7.12E-05 4.27E-04 7.12E-05i DE-131 5.80E-05 6.37E-07 5.86E-05 6.37E-07 NOTE: Results shown above are corrected for any dilution. 1 l l l 9/20/89, Page 10.2.2.1.2 - 2
i ANNUAL EXERCISE, Revision.2.0
;3 . ,
j GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE . NEW'HAMSHIRE YANKEE CHEMISTRY DEPARTMENT
. SAMPLE DESCRIPTION: RCS~ GAS
. GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89-AT 1115 RADIONUCLIDES ANALYSIS REPORT l
ACTIVITY CONCENTRATION IN- uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 6.79E-06 1.36E-06 -8.15E-06 1.36E-06 Kr-85 1.84E-07 3.69E-08 2.21E-07 3.69E-08 Kr-87. 1.07E-05 2.15E-06 1.29E-05 '2.15E-06
.Kr-88 1.76E-05 3.53E-06 2.11E-05 3.53E-06 Xe-131m 2.78E-07 5.56E-08 3.33E-07 5.56E-08 Xe-133m 1.75E-06' 3.50E-07 2.10E-06 3.50E Xe-133 5.60E-05 1.12E-05 6.72E-05 1.12E-05:
Xe-135 1.05E-05 2.10E-06 1.26E-05 2.10E-06i TOTAL 1.04E-04 2.08E-05 1.25E-04 2.08E-051 L 4 ' 9/20/89, Page 10.2.2.1.3 l' 1
o , LANNUAL EXERCISE,; Revision 2.0 j
. GAMMA SPECTRUM-ANALYSIS -
.j CANBERRA SPECTRAN-F V3.00 SOFTWARE
- )
.g NEW HAMSHIRE YANKEE CHEMISTRY-DEPARTMENT
- SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE- .
GEOMETRY' DESCRIPTION: TOP SHELF. '
- SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED.ON: 9/27/89 AT 1115 RADIONUCLIDES ANALYSIS REPORT ACTIVITY-CONCENTRATION IN uCi/cc !
NUCLIDE' MEASURED ERROR CORRECTED ERROR.
- I-131 4.40E 8.81E-06 5.28E-05 8.81E I-132 5.49E-05 ,1.10E-05 6.59E-05 1.10E-05 I-133 8.86E-05 1.78E-05 1.06E 1.78E-05 I-134- .6.65E-05 1.34E-05 7.98E-05 1 . 34E-05 I-135' 7.98Z-05 1.60E-05 9.57E-05 1.60E-05
.Cs-134: 4.08E-08 '8.19E-09 4.90E-08 8.19E-09 Cs-1371 2.04E 4.10E-09 2.45E-08 4.10E JMn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09'
.Co-60 '6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co 4.88E-08 9.78E-09 5.86E-08 9.78E-09 Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08'
. TOTAL 3.34E-04 6.69E-05 =4.01E-04 6.69E-05 l DE-131 5.66E-05 6.15E-07 5.72E-05 6 .15 E-0 7l -
NOTE: Results shown above are corrected for any dilution. 1
. .l 9/20/89, Page 10.2.2.1.3 -2
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1 a-li-j ', , 7 5 ANNUAL EXERCISE, Revision 2.0 f l;. GAMMA SPECTRUM' ANALYSIS-p ?CANBERRAISPECTRAN-F V3.00 SOFTWARE . l7 'NEWiHAMSHIRE' YANKEE CHEMISTRY. DEPARTMENT
' SAMPLE DESCRIPTION':'RCS GAS GEOMETRY DESCRIPTION: TOP SHELF
~ SAMPLE SIZE: GASLVIAL' p- .DATE COLLECTED ON:,9/27/89 AT 1130 b
, RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE. MEASURED- ERROR CORRECTED ERROR
- Kr-85m 1.63E-06' -3.27E-07 1.96E-06 '3. 27E-07' p _Kr-85 4.60E-08 9.23E-09 5.52E-08 9.23E 'Kr-87L -2.34E-06 4.69E-07 2.81E-06 4.69E-07 Kr-88 4.14E-06 8.30E-07 4.97E-06' 8.30E-07 Xe-131m 6.94E-08 1.39E-08 8.33E-08 1.39E-08, Xe-133m 4.36E-07 8.74E-08 5.23E-07 8.74E-08l
'Xea133 - 1.40E-05 2.81E-06 1.68E-05 2.81E-06l' Xe-135 2.58E-06 5.17E-07 3.09E-06 5.17E-07l TOTAL 2.52E-05 5.06E-06' 3.03E-05 5.06E-06i
(, k 8 f l k 9/20/89, Page 10.2.2.1.4 ,
ANNUAL EXERCISE, Revision 2.0-GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1130 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.40E-05 8.83E-06 5.28E-05 8.83E-06i I-132 5.09E-05 1.02E-05 6.11E-05 1.02E-05' ; I-133 8.79E-05 1.76E-05 1.05E-04 1.76E-05 I-134 5.46E-05 1.09E-05 6.55E-05 1.09E-05: I-135 7.77E-05 1.56E-05 9.33E-05 1. 56 E-05: Cs-134 4.08E-08 8.18E-09 4.90E-08 8.18E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09 Mn-.54 1.16E-08 2.33E-09 1.39E-08 2.33E-09] Co-60 6.28E-08 1.26E-08 7.54E-08 1. 26 E-08: Co-58 4.88E-08 9.78E-09 5.86E-08 9. 7 8 E-091 I Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E I TOTAL 3.15E-04 6.32E-05 3.73E-04 6.32E-05 i DE-131 5.54E-05 6.03E-07 5.60E-05 6.03E-07 ) i NOTE: Results shown above are corrected for any dilution. ) l 1 h l l 9/20/89, Page 10.2.2.1.4 - 2
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ANNUAL EXERCISE, RavisionJ2.0-n
, -i
.j GAMMA' SPECTRUM ANALYSIS-
-CANBERRA-SPECTRAN-F V3.00-SOFTWARE 1 iNEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT iSAMPLE DESCRIPTION: RCS' GAS-GEOMETRY DESCRIPTION:. TOP SHELF
. SAMPLE SIZE: GAS VIAL
-DATE-COLLECTED.ON: 9/27/89 AT.1145' RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE ' MEASURED- ERROR CORRECTED ERROR-
- Kr-85m -1.57E-06 '3.15E-07 1.89E-06 3.15E-07 Kr-85 4.60E-08 9.22E-09 .5.52E-08 9.22E-09 Kr-87 2.04E-06 4.10E-07 2.-45E-06 4.10E-07 Kr-88 3.90E 7.81E-07 4.68E-06 7.81E-07
.Xe'-131m ,
6.94E-08: 1.39E-08. 8.33E-08 1.39E-08, Xe-133m 4.34E-07~ 8.69E-08 5.21E-07 8.69E-08 Xe-133 1.40E-05 2.80E-06 1.68E-05 2.80E-06 Xe-135 2.53E-06 5.06E-07 3.03E-06 5. 06E-07l l
. TOTAL .2.46E-05 -4.92E-06 2.95E-05 4.92E-061 I l.
l- ) 9/20/89,-Page 10.2.2.1.5
- l. ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1145 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc {
NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.39E-05 8.82E-06 5.27E-05 8.82E-06' I-132 4.72E-05 9.47E-06 5.67E-05 9.47E-06 , I-133 8.71E-05 1.75E-05 1.05E-04 1.75E-05 I-134 4.48E-05 8.96E-06 5.37E-05 8. 9 6 E-0 6i I-135 7.57E-05 1.52E-05 9.09E-05 1.52E-05, Cs-134 4.08E-08 8.20E-09 4.90E-08 8.20E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09. Mn-54 1.16E-08 2.33E-09 1.39E-08 2. 3 3 E-091 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.79E-09 5.86E-08 9 . 7 9 E-09i Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08 TOTAL 2.99E-04 5.99E-05 3.59E-04 5.99E-05 DE-131 5.43E-05 5.71E-07 5.49E-05 5.71E-07 NOTE: Results shown above are corrected for any dilution. I i i 9/20/89, Page 10.2.2.1.5 - 2
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. ANNUAL ~ EXERCISE,lRavisionL2.0 4
Y f ' o . GAMMA :SPECTRi.fM LANALYSIS l iCANBERRA SPECTRAN-F V3'.00 SOFTWARE
.NEW[HAMSHIRE YANKEE CHEMISTRY _. DEPARTMENT SAMPLE DESCRIPTION::RCS GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: ' GAS VIAL DATE-'. COLLECTED ON: 9/27/89_AT 1200-
. RADIONUCLIDES' ANALYSIS, REPORT
~
ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE
. MEASURED ERROR CORRECTED ERROR Kr-85m '1.57E-06 '3.15E-07 1.89E-06. 3.15E Kr-85-- 4160E-08 9.22E-09 5.52E-08 -9.22E-09'
Kr-8'7 2.04E-06 4.11E-07 2.45E-06 4 .11E-07 :
,Kr-88: 3.90E 7.82E-07 4.68E-06 7.82E :Xe-131m .6.94E 1.39E-08 8.33E-08 1.39E-08.
Xe'-133m 4.34E-07 8.72E-08 5.22E-07 '8.72E-08' Xei133 '
.1.40E-05 2.80E-06 1.68E-05 2.80E-06 LXe-135 2.53E-06 5.06E-07 3.03E-06 5.06E-07' TOTAL .' 2 . 4 6 E-0 5 4.93E-06 2.95E-05 4 . 9 3 E-0 6 '
- l 1
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9/20/89, Page 10.2.2.1.6 _ . _ . _ _ . . _ _ . . _ . . _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ _ .._Q
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- ANNUAL EXERCISE, Revision 2.0 i
j. 1 GAMMA SPECTRUM ANALYSIS I
-i
.1'
. CANBERRA SPECTRAN-F V3.00 SOFTWARE .
NEW'HAMSHIRE YANKEE CHEMISTRY DEPARTMENT 1
' SAMPLE DESCRIPTION:-REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF:
. SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1200 I' RADIONUCLIDES ANALYSIS. REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE- MEASURED ERROR CORRECTED ERROR I-131 -4.39E-05 8.81E-06 5.27E-05 8.81E-06 I-132- 4.72E-05 9.47E-06 5.67E-05 9.47E-06
~I-133 8.71E-05 1.74E-05 1.05E-04 '1.74E-05
.I-134 4.48E-05 9.00E-06 5.38E-05 9.00E-06 I-135 17.57E-05 1.52E-05 9.09E-05 1.52E-05 Cs-134 4.08E-08 8.18E-09 4.90E-08 8.18E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09
.Mn-54 1.16E-08 2.32E-09 1.39E-08 2.32E-09 Co 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.77E-09 5.86E-08 9.77E-09 Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08
' TOTAL 2.99E-04 6.00E-05 3.59E-04 6.00E-05; DE-131 5.43E-05 5.76E-07 5.49E-05 5.76E-07 l NOTE: Results shown above are corrected for any dilution.
1 9/20/89, Page 10.2.2.1.6 - 2 1.
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t _ i. k bS t.(!} .f t , k, u ' ANNUAL EXERCISE, Revision 12.'O. o 43 N
- GAMMA SPECTRUM ANALYSIS' CANBERRA?SPECTRAN-F V3.00 SOFTWARE -
- c l NEW HAMSHIRE-YANKEE CHEMISTRY' DEPARTMENT'-
~. SAMPLE DESCRIPTION: .RCS GAS
, GEOMETRY DESCRIPTION: TOP SHELF
' SAMPLE SIZE: GAS VIAL DATE COLLECTED.ON: 9/27/89 AT 1215 RADIONUCLIDES ANALYSIS REPORT ACTIVITY. CONCENTRATION IN uCi/cc NUCLIDE'. ' MEASURED ERROR CORRECTED ERROR iKr-85m 1.51E-06 3.03E-07 1.81E-06 3.03E-07 Kr-85 o 4.60E-08 9.23E-09 5.52E-08 9.23E-09
- Kr-87 1.78E-06 3.57E-07 2.14E-06 3.57E-07 i Kr-88; 3.'66E-06 7.36E-07 4'. 4 0E 7.36E-07
~
-Xe-131mL 6.93E-08 '1.39E-08 8.32E-08 1.39E-08 Xe-133m 4~.33E-07 8.69E-08 5.20E-07 8.69E-08 Xe-133' 1.39E-05 2.80E-06 1.67E-05 2.80E-06
.Xe-135; 2.48E-06 4.97E-07 2.98E-06 4.97E-07:
. TOTAL ! 2.39E-05' 4'.80E-06 ~2.87E-05 4.80E-06 l
l 4 9/20/89, Page 10.2.2.1.7
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>> ANNUAL EXERCISE,' Revision 2.0 s
~
GAMMA SPECTRUM ANALYSIS' i-
, CANBERRA SPECTRAN-F V3.00 SOFTWARE ,
,NEW:HAMSHIRE YANKEE CHEMISTRY DEPARTMENT
?? SAMPLE. DESCRIPTION: REACTOR COOLANT SAMPLE-
. GEOMETRY DESCRIPTION: TOP SHELF' SAMPLE' SIZE:-10.0 CC VIAL DATE~ COLLECTED ON:'9/27/89 AT 1215-l RADIONUCLIDES' ANALYSIS REPORT -
ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE' MEASURED ERROR CORRECTED ERROR' I-131 4.39E-05 8.80E-06 5.27E-05 .8.80E-06 I-132 4.38E-05 8.80E-06 5.26E-05 8.80E I-133' 8.64E-05 1.73E-05 1.04E-04 1.73E-05 I-134 3.68E-05 7.39E-06 .4.41E-05 7.39E-06 I-135- -7.37E-05 ~ 1.48E-05 8.85E-05 1.48E-05. Cs-134. 4.08E-08 8.19E-09 4.90E-08 8.19E-09 ., Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54' 1.16E-08 2.32E-09 1.39E-08 2.32E-09 Co-60' 6.28E-08 1.26E-08 7.53E-08~ 1.26E-08 'j Co-58 4.88E-08 9.78E-09 5.86E-08 9.78E-09 ; Fe-59 5'.78E-08 1.16E-08 6.94E-08' 1.16E-08 l TOTAL 2.85E-04 5.71E-05 3.42E-04 5.71E-05 DE-131 5.34E-05 5.65E-07 5.40E-05 5.65E-07' NOTE: Results shown above are corrected for any dilution. l q 9/20/89, Page 10.2.2.1.7 - 2
- {
ANNUAL' EXERCISE,:Rovision 2.0- . GAMMA SPECTRUM ANALYSIS l
' CANBERRA ~SPECTRAN-F V3.'00 SOFTWARE
'NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT' e
SAMPLE DESCRIPTION: RCS GAS I, GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL' DATE COLLECTED ON: 9/27/89 AT 1230 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE -MEASURED ERROR CORRECTED ERROR Kr-85m' 1.45E-06 2.91E-07 1.75E-06 2. 91E-07; Kr-85 4.60E-08. 9.21E-09 5.52E-08 9. 21E-091 Kr-87 1.56E-06 3.12E-07 1.87E-06 3.12E-07; Kr-88. 3.45E-06' 6.93E-07 4.14E-06 6.93E-07' Xe-131m 6.93E-08 1.39E-08 8.32E-08 1.39E-08,- Xe-133m 4.31E-07 8.64E-08 5.18E-07 8.64E-081 Xe-133 1.39E-05 2.80E-06 1.67E-05 2. 80E-06i
'Xe-135 2.43E-06 4.88E-07 2.92E-06 4.88E-07!
TOTAL 2.34E-05 4.69E-06 2.81E-05 4.69E-061 l l k 9/20/89, Page 10.2.2.1.8
c ANNUAL EXERCISE,-Revision 2.0 h GAMMA SPECTRUM ANALYSIS i CANBERRA SPECTRAN-F V3.00 SOFTWARE o NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION:. REACTOR COOLANT SAMPLE
- GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC~ VIAL DATE COLLECTED ON: 9/27/89 AT 1230 RADIONUCLIDES ANALYSIS REPORT i ACTIVITY CONCENTRATION IN uCi/cc l NUCLIDE MEASURED ERROR CORRECTED ERROR I-131- 4.38E-05 8.80E-06 5.26E-05 8.80E-06 I-132 '4.06E-05' 8.16E-06 4.88E-05 8.16E-06 I-133 8.57E-05 1.72E-05 1.03E-04 '1.72E-05
'I-134 3.02E-05 6.06E-06 3.62E-05 6.06E-05 I-135 7.18E-05 '1.'44E-05 8.62E-05 1.44E-05 Cs-134 4.08E-08 8.19E-09 4.90E-08 8.19E-09 CO-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09
'Mn-54 1.16E-08 2.33E-09 1.39E-98 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08
'Co-58 4.88E-08 9.77E-09 5.85E-08 9.77E-09 Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08 TOTAL 2.72E-04 5.46E-05 3.27E-04 5.46E-05; DE-131 5.25E-05 5.26E-07 5.30E-05 5.26E-071 NOTE: Results shown above are corrected for any dilution.
9/20/89, Page 10.2.2.1.8 - 2 ,
- l
\;
' ANNUAL EXERCISE,'. Revision'2.O, ,
a '. _ 1 Oi _.: 1 h , .4 , t <
- 3. ,
m'~ ' GAMMA SPECTRUM ANALYSIS-a: CANBERRA'SPECTRAN-F V3.00, SOFTWARE-NEW HAMSHIRE. YANKEE CHEMISTRY DEPARTMENT 'I
. SAMPLE' DESCRIPTION: RCS GAS: l GEOMETRY DESCRIPTION: TOP SHELF: , .,.; SAMPLE SIZE:' GAS-VIAL DATE COLLECTED ON: 9/27/89 AT'1245 .
RADIONUCLIDES' ANALYSIS REPORT l.. ACTIVITY CONCENTRATION IN- uCi/cc
.NUCLIDE' MEASURED ERROR CORRECTED ERROR Kr-85m l'.40E-06. 2.81E 1.68E-06 2.81E-07p
- Kr-85 4.60E-08 9. 2 4 E-0 9 -. 5.53E-08 9.24E-09!
Kr 1.36E-06 '2.72E-071- .1.63E-06 2.72E-07;
.Kr-88 3.24E 6.50E-07 3.89E-06 6.50E-07'.
Xe-131m 6.92E-08 1.39E-08 8.31E-08 1.39E-08.
- Xe-133m 4.30E-07: :8.60E-08 5.16E-07 8.60E-08 I Xe-133 1.39E-05> 2.79E-06 1.67E-05 2.79E-06 Xe-135 2.39E-06 4.80E-07 2.87E-06 4.80E-07' TOTAL- 2.28E-05 4.58E-06 '2.74E-05 4.58E-06:
n 9/20/89, Page 10.2.2.1.9
Q, , H
-ANNUAL'.-EXERCISE,cRsvision 2.0 L
. GAMMA SPECTRUM ANALYSIS 4
CANBERRA SPECTRAN-F V3.00' SOFTWARE . NEW HAMSHIRE. YANKEE CHEMISTRY. DEPARTMENT-
- SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE is GEOMETRY DESCRIPTION:. TOP SHELF SAMPLE SIZE: 10.0 CC VIAL I
DATE COLLECTED ON: 9/27/89 AT 1245 RADIONUCLIDES ANALYSIS REPORT
. ACTIVITY CONCENTRATION IN- uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 '4.38E-05 8.76E-06 5.26E-05 8.76E-06 I-132 3.77E-05 7.57E-06 4.53E-05 7.57E I-133: 8.50E-05 1.70E 1.02E-04 1.70E-05'
- I-134. 2.48E-05 4.96E 06 2.97E-05 .4.96E-06 I-135 7.00E-05 1.40E-05 8.40E-05 1.40E-05 Cs-134 4.08E-08 8.18E-09 4.90E 8.18E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54 1.16E-08 2.32E-09 1.39E-08 2.32E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 .1.26E-08 Co 4.88E-08 9.76E-09 5.85E-08 9.76E-09 Fe-59 5.78E-08 1.16E-08 6.93E-08 1.16E TOTAL. 2.61E-04 5.24E-05 3.14E-04 5. 2 4 E-0 5:
- DE-131 5.17E-05 5.48E-07 5.23E-05 5. 4 8E-07' NOTE: Results shown above are corrected for any dilution.
l l 9/20/89, Page 10.2.2.1.9 - 2
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'1ANNUALiEXERCISE,' Revision 2.0 k
,,I
!E
! GAMMA SPECTRUM ANALYSIS-CANBERRA SPECTRAN-F,V3.00: SOFTWARE ,
NEW HAMSHIRE' YANKEE CHEMISTRY.DEPA'RTMENT
.' SAMPLE. DESCRIPTION 5-RCS GAS GEOMETRY' DESCRIPTION: TOP SHELF.
SAMPLE' SIZE: GAS ~ VIAL' [ t.
. DATEJCOLLECTED'ON: l9/27/89^AT.1300 p ,
. RADIONUCLIDES ANALYSIS REPORT
- ACTIVITY' CONCENTRATION IN uCi/cc
- NUCLIDE' MEASURED ~ ERROR CORRECTED ERROR Kr-85mu 1.35E-06. 2.70E-07 1.C2E-06 2.70E-07'.
Kr-85' 4.60E-08' 9.22E-09 5.52E-08 9.22E-09
.. Kr-87 1.18E-06 2.37E-07 1.42E-06 2.'37E-07'
. Kr-88L 3.05E-06~ 6.11E-07 3.66E-06 6.11E - Xe-131m. 6.92E-08= 1.39E 8.31E-08 1.'39E-08 Xe-133m 4.29E-07 8.58E-08 5.14E-07 8;58E-08
.Xe-l'33 '1.39E-05. 2.79E 1.67E-05 2'.79E-06:
Xe-135~ .2.34E-06 4.70E-07 2.81E-06 4.70E-07' TOTAL: 2.24E-05 4.48E-06 2.6BE-05 ~ 4.48E-06i y
, , 9/20/89, Page 10.2.2.1.10 1_ ._.C_.__[_m
. _ _ _ _ _ _ _.__i__ ._ _ . _ _ _ _
- j. ,
C ' u u 6i* -
] ANNUAL EXERCISE / Revision'2.'O ?
j$5 " 14', 01 U: GAMMA SPECTRUM. ANALYSIS m O %. k n ! CANBERRA SPECTRAN-F.V3.00' SOFTWARE. . u [ 'NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT. 6 1 SAMPLE DESCRIPTION: REACTOR COOLANT. SAMPLE GEOMETRY DESCRIPTION: TOP SHELF
, Sh . SAMPLE SIZE: 10.0 CC VIAL ,,_ DATE COLLECTED ON: .9/27/89 AT 1300 i
RADIONUCLIDES' ANALYSIS REPORT-L ACTIVITY. CONCENTRATION IN uCi/cc b , 'NUCLIDE MEASURED ERROR CORRECTED ERROR h [I-131 4.38E-05 -8.78E-06 5.25E-056 8.78E-06 I-132 3.50E-05 7.00E-06 4.20E-05. 7.00E-06
'I-l'33 -8.43E-05 1.69E-05 1.01E-04 1.69E-05
, -I-134 '2.03E-05 '4.06E-06 2.44E 4.06E-06 I-135 6.81E-05 1.36E 8.18E-05 1.36E Cs-134 4.08E-08 8.20E-09. 4.91E-081 8.20E-09 Cs .137 2.04E-08 4.09E-09 2.45E-08 4.09E Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E 1.26E-08 7.53E-08 1.26E-08 Co-58 4.88E-08 9.78E 5.86E-08 9.78E-09 Fe-59 5.78E-08 1.16E-08 6.93E-08 1.16E-08 i
TOTAL 2.52E-04 5.04E-05 3.02E-04 5.04E-05 ! DE-131 5.10E-05 5.24E-07 5.16E-05' 5.24E-071
- NOTE: Results shown above are corrected for any dilution.
9/20/89, Page 10.2.2.1.10 - 2 i. r
7, ., . ky;[ !-u : ANN AL EXERCISE , ) Rhvision I 2.. O
- g a.
is > GAMMA' SPECTRUM ANALYSIS' F CANBERRA SPECTRAN-F V3.00 SOFTWARE'- L ,
- NEW HAMSHIRE YANKEE- CHEMISTRY DEPARTMENT k'; ' SAMPLE DESCRIPTION: RCS GAS.
GEOMETRY DESCRIPTION: TOP SHELF
- SAMPLE SIZE: GAS VIAL DATE' COLLECTED ON: 19/27/89 AT.1315 RADIONUCLIDES' ANALYSIS REPORT L <
ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR. CORRECTED ERROR Kr-85m' 1.30E-06 2.59E-07 1.55E-06 2.59E-07; Kr-85 4.60E-08 9.21E-09 5.52E-08 9.21E-09'
.Kr-87 1.03E-06 2.07E-07 1.24E-06 2.07E Kr-88 -2.87E-06 5.75E-07 3.45E-06 5 . 7 5 E-07 '-
.Xe-131m 6.92E-08 1.38E-08 8.30E-08 1.38E-08:
'Xe-133m 4.27E-07 8.57E 5.13E-07 8. 57E-08:
Xe-133 1.39E-05 2.78E-06 1.66E-05 2.78E-06i Xe -13 5 .2.30E-06 4.60E-07 2.76E-06 4.60E-07' TOTAL 2.19E-05 4.39E-06 2.63E-05 4. 3 9E-06i k 9/20/89, Page 10.2.2.1.11 _-_. - ____-__-_--_____-__---_-_--___-_-__________________-_a
ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS ' CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION
- REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1325 I I
RADIONUCLIDES ANALYSIS REPORT j i ACTIVITY CONCENTRATION IN uCi/cc l NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.37E-05 8.77E-06 5.25E-05 8.77E-06 I-132 3.24E-05 6.51E-06 3.89E-05 6.51E-06 I-133 8.36E-05 1.67E-05 1.00E-04 1.67E-05 l I-134 1.67E-05 3.34E-06 2.00E-05 3.34E-06 I-135 6.64E-05 1.33E-05 7.97E-05 1.33E-05 Cs-134 4.08E-08 8.19E-09 4.90E-08 8.19E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.78E-09 5.85E-08 9.78E-09 Fe-59 5.78E-08 1.16E-08 6.94E-08 1.16E-08' TOTAL 2.43E-04 4.87E-05 2.92E-04 4.87E-051 DE-131 5.04E-05 5.28E-07 5.09E-05 5. 28 E-07l NOTE: Results shown above are corrected for any dilution. 9/20/89, Page 10.2.2.1.11 - 2
ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE - NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1330 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 1.25E-06 2.50E-07 1.50E-06 2.50E-07l Kr-85 4.60E-08 9.21E-09 5.52E-08 9.21E-09! Kr-87 9.02E-07 1.81E-07 1.08E-06 1.81E-07' Kr-88 2.70E-06 5.41E-07 3.24E-06 5.41E-07 Xe-131m 6.91E-08 1.39E-08 8.30E-08 1.39E-08i Xe-133m 4.26E-07 8.52E-08 5.11E-07 8.52E-081 Xe-133 1.39E 05 2.77E-06 1.66E-05 2.77E-06 Xe-135 2.25E-06 4.52E-07 2.71E-06 4.52E-07 TOTAL 2.15E-05 4.30E-06 2.5SE-05 4.30E-06' 9/20/89, Page 10.2.2.1 12
ANNUAL EXERCISE, Revision 2.0 I GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE . NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1330 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.37E-05 8.78E-06 5.25E-05 8.78E-06i , I-132 3.01E-05 6.03E-06 3.61E-05 6.03E-06 I-133 8.29E-05 1.66E-05 9.95E-05 1.66E-05 I-134 1.37E-05 2.75E-06 1.64E-05 2.75E-06 I-135 6.47E-05 1.30E-05 7.76E-05 1.30E-05 Cs-134 4.08E-08 8.21E-09 4.91E-08 8.21E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 i4n-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.77E-09 5.85E-08 9.77E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08 TOTAL 2.35E-04 4.72E-05 2.82E-04 4.72E-05 DE-131 4.98E-05 5.38E-07 5.04E-05 5.38E-071 NOTE: Results shotin above are corrected for any dilution. l l I i 1 9/20/89, Page 10.2.2.1.12 - 2
i ' x ,
-?
l[M;h v- !]1 H -ANNUAL EXERCISE,' Revision 2.0. E , .. , ( y
)
o GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE t
-NEW HAMSHIRE-YANKEE CHEMISTRY DEPARTMENT
. SAMPLE: DESCRIPTION: RCS GAS
-GEOMETRY DESCRIPTION: TOP SHELF
' ' SAMPLE' SIZE: GAS VIAL ,
DATE COLLECTED ON: 9/27/89 AT 1345 1 ]i RADIONUCLIDES ANALYSIS' REPORT-
'l J
-ACTIVITY CONCENTRATION IN uCi/cc
, NUCLIDE. MEASURED ERROR CORRECTED' ERROR r
Kr-85m' 1.20E-06 2.41E-07 1.44E-06 2.41E-07 Kr-85' 4.60E-08 9.25E-09 5.53E-08 9.25E-09i Kr-87 7.87E-07 1.57E-07 9.14E-07 1.57E-07 Kr-88 2.54E-06 5.09E-07 3.05E-06 5.09E-07 Xe-131m 6.91E-08 1.39E-08 8.29E-08 1.39E-08 Xe-133m 4.24E-07 8.52E-08 5.10E-07 8.52E-08 Xe-133 1.38E-05 2.77E-06 1.66E-05 2. 77E-06: Xer135. 2.21E-06 4.44E-07 2.66E -06 4.44E-07' TOTAL 2.11E-05 4.23E-06 2.53E-05 4.23E-068 Y 1 l i i 9/20/89, Page 10.2.2.1.13
if l I !
'l
; ANNUAL' EXERCISE, Revision 2'.0 ]
O 1 L
-i GAMMA-SPECTRUM ANALYSIS .
l l
)
l CANBERRA SPECTRAN-F V3.00 SOFTWARE . j 1 F-a
.NEW HAMSHIRE' YANKEE CHEMISTRY DEPARTMENT SAMPLE-DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE-COLLECTED ON: 9/27/89 AT 1345 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE' MEASURED ERROR ' CORRECTED ERROR I-131 4.36E-05 8.74E-06 5.24E-05 8.74E-06 I-132 2.79E-05 5.59E-06 3.35E-05 5.59E-06 I-133 S.22E-05 1.65E-05 9.87E-05 1.65E-05 I-134 1.12E-05 2.25E-06 1.35E-05 2.25E-06
- I-135 6.30E-05 1.26E-05 7.56E-05 1.26E-05 Cs-134 4.08E-08 8.18E-09 4.90E-08 8.18E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54 1.16E-08 2.32E-09 1.39E-08 2.32E-09
' Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.88E-08 9.79E-09 -5.85E-08 9.79E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08 TOTAL 2.28E-04 4.57E-05 2.74E-04 4.57E-05 DE-131 4.93E-05 5.25E-07 4.98E-05 5. 25E-07i NOTE: Results shown above are corrected for any dilution.
l 9/20/89, Page 10.2.2.1.13 - 2
i t i
~ ANNUAL EXERCISE, Revision 2.0 l
l GAMMA SPECTRUM ANALYSIS i i i CANBERRA SPECTRAN-F V3.00 SOFTWARE l NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT ! SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE.bi2E: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1400 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 1.15E-06 2.32E-07 1.39E-06 2.32E-07 g Kr-85 4.60E-08 9.22E-09 5.52E-08 9.22E-09! Kr-87 6.86E-07 1.38E-07 8.24E-07 1.38E-071 Kr-88 2.39E-06 4.80E-07 2.87E-06 4. 80E-07: Xe-131m 6.90E-08 1.39E-08 8.29E-08 1.39E-08j j Xe-133m 4.23E-07 8.47E-08 5.08E-07 8.47E-08: Xe-133 1.38E-05 2.77E-06 1.66E-05 2. 77 E-06l Xe-135 2.17E-06 4.35E-07 2.60E-06 4 . 3 5 E-0 7' TOTAL 2.08E-05 4.16E-06 2.49E-05 4.16E-068 I 9/20/89, Page 10.2.2.1.14
1
. ANNUAL EXERCISE, Revision 2.0
( GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE. YANKEE CHEMISTRY DEPARTMENT F SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL .i DATE COLLECTED ON: 9/27/89 AT 1400 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR
.I-131 4.36E-05 8.75E-06 '5.24E-05 8.75E-06.
I-132 2.59E-05 5.18E-06 3.10E-05 5 .18 E--0 6 I-133 8.15E-05 1.63E-05 9.78E-05 1.63E-05 I-134 9.22E-06 1.85E-06 1.11E-05 1.85E-06 I-135 6.13E-05 1.23E-05 7.37E-05 1.23E-05 Cs-134 4.08E-08 8.18E-09 4.90E-08 8.18 E- 0 9 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-L9
' Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-Or Co-60 6.28E-08 1.26E-08 7.53E-08 1.26E-08 Co-58 4.87E-08 9.76E-09 5.85E-08 9.76E-0)
Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08 TOTAL 2.22E-04 4.44E-05 2.66E-04 4.44E-05: DE-131 4.88E-05 4.91E-07 4.93E-05 4.91E-07 NOTE: Results shown above are corrected for any dilution. I 9/20/89, Page 10.2.2.1.14 - 2 , I _ _ _ _ _ _ - - - - _ __ _ --__ _ l
i l ANNUAL EXERCISE, Revision 2.0 l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1415 i RADIONUCLIDES ANALYSIS REPORT l ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR i Kr-85m 1.11E-06 2.23E-07 1.33E-06 2.23E-07, ! Kr-85 4.60E-08 9.24E-09 5.53E-08 9.24E-09' Kr-87 5.99E-07 1.20E-07 7.19E-07 1. 2 0E-07 Kr-88 2.25E-06 4.52E-07 2.70E-06 4.52E-07 Xe-131m 6.90E-08 1.39E-08 8.29E-08 1.39E-08 Xe-133m 4.22E-07 8.44E-08 5.06E-07 8.44E-08' Xe-133 1.38E-05 2.76E-06 1.66E-05 2 . 76E-06i Xe-135 2.13E-06 4.27E-07 2.56E-06 4 . 27E-07! TOTAL 2.04E-05 4.09E-06 2.45E-05 4.09E-063 1 9/20/89, Page 10.2.2.1.15
P 1 ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00. SOFTWARE I NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY NSCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1415 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERRCR CORRECTED ERROR I-131 4.36E-05 8.72E-06 5.23E-05 8.72E-06 I-132 2.40E-05 4.81E-06 2.88E-05 4.81E-06 I-133 8.08E-05 1.62E-05 9.70E-05 1.62E-05 I-134 7.57E-06 1.52E-06 9.09E-06 1.52E-06 I-135 5.98E-05 1.20E-05 7.17E-05 1.20E-05 Cs-134 4.08E-08 8.18E-09 4.90E-08 8.18E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09 Mn-54 1.16E-0C 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.87E-08 9.75E-09 5.85E-08 9.75E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16 E-08: TOTAL 2.16E-04 4.33E-05 2.59E-04 4 . 3 3 E-05: DE-131 4.84E-05 5.06E-07 4.89E-05 5.06E-071 NOTE: Results shown above are corrected for any dilution. 1 1 , 9/20/89, Page 10.2.2.1.15 - 2 E---------____-___-_____ _ _ _ _ _ _ _ _ _ _ _
L L ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF ! SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1430 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR- CORRECTED ERROR Kr-85m 1.07E-06 2.14E-07 1.28E-06 2.14E-07; Kr-85 4.60E-08 9.23E-09 5.52E-08 9.23E-091 Kr-87 5.22E-07 1.05E-07 6.27E-07 1.05E-07' Kr-88 2.12E-06 4.25E-07 2.54E-06 4.25E-07' Xe-131m 6.89E-08 1.38E-08 8.27E-08 1.38E-08! I Xe-133m 4.20E-07 8.43E-08 .5.04E-07 8.43E-081 Xe-133 1.38E-05 2.75E-06 1.65E-05 2.75E-06j Xe-135 2.09E-06 4.19E-07 2.51E-06 4.19E-071 TOTAL 2.01E-05 4.03E-06 2.41E-05 4.33E-06i 9/20/89, Page 10.2.2.1.16 i
I ANNUAL EXERCISE, Revision 2.0 i r. GAMMA SPECTRUM ANALYSIS l CANBERRA SPECTRAN-F V3'.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: '10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1430 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc ! NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.35E-05 8.75E-06 5.23E-05 8.75E-06 I-132 2.22E-05 4.47E-06 2.67E-05 4.47E-06 I-133 8.02E-05 1.60E-05 9.62E-05 1.60E-05 I-134 6.21E-06 1.24E-06 7.45E-06 1.24E-06 I-135 5.82E-05 1.16E-05 6.99E-05 1.16E-05 Cs-134 4.08E-08 8.19E-09 4.90E-08 8.19E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.53E-08 1.26E-08 Co-58 4.87E-08 9.78E-09 5.85E-08 9.78E-09 Fe-59 5.77E-08 1.15E-08 6.92E-08 1.15E-08' TOTAL 2.11E-04 4.22E-05 2.53E-04 4.22E-05: DE-131 4.80E-05 S.06E-07 4.85E-05 5.06E-071 NOTE: Results shown above are corrected for any dilution. l I l l l l l 9/20/89, Fage 10.2.2.1.16 - 2
7__----- P j i 1 ANNUAL EXERCISE, Revision 2.0 I i i GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE
]
NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT ! l SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF 4 SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1445 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc j NUCLIDE MEASURED ERROR CORRECTED ERROR
-Kr-85m 1.03E-06 2.06E-07 1.23E-06 2.06E-07l Kr-85 4.60E-08 9.21E-09 5.52E-08 9. 21E-091 Kr-87 '4.56E-07 9.16E-08 5.47E-07 9.16 E-08!
Kr-88 1.17E-06 3.99E-07 2.39E-06 3.99E-07' Xe-131m 6.89E-08 1.38E-08 8.27E-08 1. 3 8 E-08i Xe-133m 4.19E-07 8.41E-08 5.03E-07 8.41E-081 . Xe-133 1.38E-05 2.76E-06 -1.65E-05 2.76E-06 l Xe-135 2.05E-06 4.11E-07 2.46E-06 4.11E-07
. TOTAL 1.98E-05 3.97E-06 2.393-05 3.97E-06.
l l: 9/20/89, Page 10.2.2.1.17 ;
1 l ANNUAL EXERCISE, Revision 2.0 l I l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE I NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1445 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.35E-05 8.71E-06 5.22E-05 8.71E-06 I-132 2.06E-05 4.15E-06 2.48E-05 4.15E-06 I-133 7.95E-05 1.59E-05 9.54E-05 1.59E-05 I-134 5.10E-06 1.02E-06 6.12E-06 1.02E-06 I-135 5.67E-05 1.13E-05 6.81E-05 1.13E-05 Cs-134 4.08E-08 8.19E-09 4.90E-08 8.19E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54 1.16E-08 2.32E-09 1.39E-08 2.32E Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.87E-08 9.77E-09 5.85E-08 9.77E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08 TOTAL 2.06E-04 4.12E-05 2.47E-04 4.12E-05 DE-131 4.76E-05 4.79E-07 4.81E-05 4.79E-0Z NOTE: Results shown above are corrected for any dilution. 9/20/89, Page 10.2.2.1.17 - 2
ANNUAL EXERCISE, Revision 2.0 l GAMMA SPECTRUM ANALYSIS I CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1500 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE- MEASURED ERROR CORRECTED ERROR Kr-85m 9.88E-07 1.98E-07 1.19E-06 1.98E-07 Kr-85 4.60E-08 9.23E-09 5.52E-08 9.23E-09 Kr-87 3.98E-07 7.96E-08 4.77E-07 7.96E-08: Kr-88 1.87E-06 3.75E-07 2.25E-06 3.75E-07' Xe-131m 6.89E-08 1.38E-08 8.26E-08 1.38E-08! Xe-133m 4.17E-07 8.36E-08 5.01E-07 8.36E-081 Xe-133 1.37E-05 2.75E-06 1.65E-05 2.75E-061 Xe-135 2.01E-06 4.04E-07 2.41E-06 4.04E-07f TOTAL 1.95E-05 3.92E-06 2.35E-05 3.92E-06 9/20/89, Page 10.2.2.1.18
1 ANNUAL EXERCISE, Revision 2.0 1 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1500 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc l NUCLIDE MEASURED ERROR CORRECTED ERROR . I-131 4.34E-05 8.71E-06 5.22E-05 8.71E-06 I-132 1.91E-05 3.84E-06 2.30E-05 3.84E-06 I-133 7.88E-05 1.58E-05 9.47E-05 1.58E-05 I-134 4.18E-06 8.40E-07 5.02E-06 8.40E-07 I-135 5.52E-05 1.11E-05 6.63E-05 1.11E-05 Cs-134 4.08E-08 8.20E-09 4.90E-08 8.20E-09 Cs-137 2.04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.87E-08 9.77E-09 5.85E-08 9.77E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08 TOTAL 2.01E-04 4.04E-05 2.41E-04 4.04E-05j DE-131 4.73E-05 5.17E-07 4.78E-05 5.17E-071 NOTE: Results shown above are corrected for any dilution. 9/20/89, Page 10.2.2.1.18 - 2
p ANNUAL EXERCISE, Ravision 2.0 - n..; , j l GAMMA SPECTRUM ~ ANALYSIS l s , .., CANBERRA SPECTRAN-F V3.00 SOFTWAREf NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT. SAMPLE DESCRIPTION: RCS GAS GEOMETRY DESCRIPTION: TOP SHELF i- . SAMPLE SIZE: GAS VIAL 4 DATE COLLECTED ON:'9/27/89 AT 1515 RADIONUCLIDES ANALYSIS REPORT ACTIVITY' CONCENTRATION IN .uCi/cc NUCLIDE . MEASURED' ERROR CORRECTED ERROR l Kr-85m- 9.50E-07 1.91E-07 1.14E-06 1.91E-07; i s 'Kr-85 4.60E-08 9.24E-09 5.53E-08 9. 2 4 E-0 9i Kr-87 3.47E-07 6.94E-08 4.16E-07 6.94E-08 Kr 1.76E-06 3.54E-07 2.12E-06 3.54E-07' Xe-131m 6.88E 1.38E-08 8.26E-08 1.38E-08. Xe-133m 4.16E-07 8.36E-08 5.00E-07 8.36E-08:- Xe-133 1.37E-05 2.75E-06 1.65E-05 2.75E-06,
-Xe-135 1.97E-06 3.96E-07 2.37E-06 3.96E-07i TOTAL 1.93E-05 3.87E-06 2.32E-05 3.87E-06'
( 9/20/89, Page 10.2.2.1.19
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ANNUA 2/ EXERCISE,= Revision 2.0
.)
k
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# l GAMMA SPECTRUM. ANALYSIS 'I L CANBERRA SPECTRAN-F'V3.00 SOFTWARE' I 'NEW'HAMSHIRE YANKEE CHEMISTRY-DEPARTMENT
' SAMPLE' DESCRIPTION: . REACTOR COOLANT SAMPLE i- , GEOMETRY DESCRIPTION: TOP SHELF
; SAMPLE-SIZE:.10.0 CC VIAL TDATE COLLECTED ON: 9/27/89_AT 1515 RADIONUCLIDES ANALYSIS REPORT ,
' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE' MEASURED ERROR CORRECTED ERROR-
=I-131- 4.34E-05 8.70E 5.21E 8.70E-06 I-132' 1.77E-05 3.55E-06 '2.13E-05 3.55E-06 v I-133 7.82E-05 1.57E-05 9.39E-05 1.57E-05 I-134 3.43E-06 6.90E-07 4.12E-06 6.90E-07
.I-135 ~5.38E-05 1.08E-05 6.46E 1.08E-05
~Cs-134' 4.08E-08 8.17E-09 4.90E 8.17E-09 Cs-137 2.'04E-08 4.09E-09 2.45E-08 4.09E-09 Mn-54. 1.16E-08 2.33E-09 1.39E-08 2.33E-09 1 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58' 4.87E-08 9.75E-09 5.85E-08 9.75E-09 Fe-59 5.77E-08 1.16E-08 6.93E-08 1.16E-08
. TOTAL 1.97E-04 3.95E-05 2.36E-04 3.95E-05'
.DE-131 4.69E-05 5.02E-07 4.74E-05 5.02E-07)
NOTE: Results shown above are corrected for any dilution. 1 9/20/89, Page 10.2.2.1.19 - 2
ANNUAL EXERCISE, Revision 2.0 l' l GAMMA SPECTRUM ANALYSIS l CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS CAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1530 i RADIONUCLIDES ANALYSIS REPORT ( i ! ACTIVITY CONCENTRATION IN uCi/cc i I NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 9.14E-07 1.83E-07 1.10E-06 1.83E-07. Kr-85 4.60E-08 9.24E-09 5.53E-08 9.24E-09l Kr-87 3.03E-07 6.06E-08 3.63E-07 6.06E-08l Kr-88 1.66E-06 3.33E-07 1.99E-06 3.33E-07' Xe-131m 6.88E-08 1.38E-08 8.26E-08 1.38E-08. Xe-133m 4.15E-07 8.32E-08 4.98E-07 8.32E-081 Xe-133 1.37E-05 2.74E-06 1.64E-05 2.74E-061 l Xe-135 1.94E-06 3.88E-07 2.32E-06 3.88E-071 TOTAL 1.90E-05 3.81E-06 2.29E-05 3.81E-06' l { 1 i 1 I 9/20/89, Page 10.2.2.1.20
___7__ I ANNUAL EXERCISE, Revision 2.0 N, I l GAMMA SPECTRUM ANALYSIS l CANBEFia SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT 1 SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE l GEOMETRY DESCRIPTION: TOP SHELF ; SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1530 I RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.34E-05 8.71E-06 5.21E-05 8.71E-06 I-132 1.65E-05 3.30E-06 1.98E-05 3.30E-06 I-133 7.75E-05 1.55E-05 9.31E-05 1.55E-05 I-134 2.82E-06 5.66E-07 3.38E-06 5.66E-07 l I-135 5.24E-05 1.05E-05 6.29E-05 1.05E-05 Cs-134 4.08E-08 8.19E-09 4.90E-08 8.19E-09 Cs-137 2.04E-08 4.10E-09 2.45E-08 4.10E-09 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 Co-60 6.28E-08 1.26E-08 7.54E-08 1.26E-08 Co-58 4.87E-08 9.77E-09 5.85E-08 9.77E-09 Fe-59 5.77E-08 1.16E-08 6.92E-08 1.16E-08' TOTAL 1.93E-04 3.87E-05 2.32E-04 3.87E-05 DE-131 4.66E-05 4.95E-07 4.71E-05 4.95E-07 NOTE: Results shown above are corrected for any dilution. l 1
)
9/20/89, Page 10.2.2.1.20 - 2 I _. ._. _ - _ _ _ _ - _ - _ _ .-___-______a
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u% c . ANNUAL EXERCISE, Revision'2.0 GAMMA' SPECTRUM ANALYSIS CANBERRA ~SPECTRAN-F V3.00 SOFTWARE , NEW HAMSHIRE. YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: RCS GAS
. GEOMETRY DESCRIPTION: TOP SHELF'
.,. SAMPLE SIZE: GAS ~ VIAL E DATE; COLLECTED ON: 9/27/89 AT 1545 RADIONUCLIDES. ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDEL MEASURED ERROR CORRECTED ERROR-
.Kr-85m 8.80E-07. 1.77E-07 1.06E-06 1.77E-07 i Kr-85 4.60E-08 .9.24E-09 5.53E-08 9.24E-09l-Kr-87 2.64E-07 5.29E-08 3.17E '5.29E-08, Kr-88 1.56E-06 3.13E-07 1.87E-06 3.13E-07' Xe-131m 6~87E . 1.38E-08 8.25E-08 1.38E-08! 1 Xe-133m .4113E-07' 8.28E-08 4.96E-07 8.28E-081 Xe-133 1.37E-05 2.74E-06 1.64E-05 2.74E-06l Xe-135 1.90E-06 3.81E-07 2.28E-06 3 . 81E-071 TOTAL. 14 88E-05 3.77E 2.26E-05 3.77E i 1
i
\
l 9/20/89, Page 10.2.2.1.21 l
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l
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i ' s l. JANNUAL EXERCISE, Revision'2.0 l e , , I' GAMMA SPECTRUMiANALYSIS , c1
; CANBERRA SPECTRAN-F.V3.00 SOFTWARE ,
j l< i SEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT. ,
. SAMPLE DESCRIPTION: REACTOR COOLANT SAMPLE- ;i GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL ]
)
DATE COLLECTED ON: 9/27/89 AT 1545 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION'IN uCi/cc NUCLIDE -MEASURED ERROR CORRECTED ERROR l I-131~ 4.33E-05' 8.70E-06 5.20E-05 8.70E-06 j I-132 1.53E-05 3.06E-06 1.83E-05 3.06E-06 1
'I-133 7.69E-05 1.54E-05 9.23E-05 '1.54E-05' I-134~ '2.31E 4.64E-07 2.78E-06 4.64E-07 I-135 5.11E-05 1.02E-05 6.13E-05 1.02E-05 Cs-134 4.08E-08 8.20E-09 4.90E-08 8.20E-09 Cs-137 '2.04E-08 4.10E-09 2.45E-08 4.10E-09 1 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 i Co-60 6.28E-08 1.26E-08 7.53E-08 1.26E-08 Co-58 4.87E-08 9.76E-09 5.85E-08 9.76E-09 Fe-59 5.77E-08 1.15E-08 6.92E-08 1.15E TOTAL 1.89E-04 3.79E-05 2.27E-04 3.79E-05 DE-131 4.64E-05 4.67E-07 4.68E-05 4.67E-07. j NOTE: Results shown above are corrected for any dilution.
9/20/89, Page 10.2.2.1.21 - 2
I L ANNUAL EXERCISE, Revision 2.0 i GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION:.RCS GAS j GEOMETRY DESCRIPTION: TOP SHELF ' i' SAMPLE SIZE: GAS VIAL DATE COLLECTED ON: 9/27/89 AT 1600 RADIONUCLIDES' ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR .j
.Kr-85m 8.4/ -07 1.70E-07 1.02E-06 1.70E-07 Kr-85 4.60E-08 9.23E-09 5.52E-08 9.23E-09 Kr-87 2.30E-07 4.62E-08 2.77E-07 4.62E-08 Kr-88. 1.47E-06 2.94E-07 1.76E-06 2.94E-07!
Xe-131m 6.87E-08 1.38E-08 8.25E-08 1.38E-08i Xe-133m 4.12E-07 8.24E-08 4.94E-07 8.24E-081 Xe-133 1.37E-05 2.74E-06 1.64E-05 2.74E-061 Xe-135 1.86E-06 3.73E-07 2.24E-06 3.73E-07l TOTAL 1.86E-05 3.73E-06 2.23E-05 3.73E-06; l l l 9/20/89, Page 10.2.2.1.22 i
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- ANNUAL. EXERCISE,eRevision 2.0 t
w o j-- , GAMMA SPECTRUM ANALYSIS 40 r CANBERRA'SPECTRAN-F V3~00 . SOFTWARE . NEW HAMSHIRE'_ YANKEE CHEMISTRY _. DEPARTMENT SAMPLE-DESCRIPTION: REACTOR COOLANT SAMPLE
' GEOMETRY DESCRIPTION: TOP' SHELF
. SAMPLE SIZE: '10.0 CC VIAL f' .DATE COLLECTED ON: 9/27/89 AT.1600 RADIONUCLIDES ANALYSIS REPORT , '
+
ACTIVITY CONCENTRATION IN -uCi/cc A ' NUCLIDE-- MEASURED ERROR CORRECTED- ERROR I-131' -- 4.33E-05 8.68E-06 5.20E-05 8.68E-06 I-132 1.42E 2.84E-06 1.70E-05 2.84E-06 I-133: 7.63E-05 1.53E-05 9.16E-05. 1.53E I-134- 1.90E-06 3.80E-07 2.28E-06 3.80E-07
'I-135! '4.97E 9.98E-06 5.97E-05~ 9.98E-06 Cs-134~ 4.08E '8.20E-09 4.90E-08 8.20E-09 Cs-137 2.04E-08 4.10E-09 2.45E 4.10E-09 Mn-54 1.16E-08 2.33E-09 1.39E-08 2.33E-09 ,
Co-60 6.28E-08 1.26E-08 7.53E-08 l'.26E-08
.Co-58 4.87E-08 9.78E-09' 5.85E-08 9.78E-09 Fe-59 '5.76E-08 1.16E-08 6.92E-08 1.16 E-0 8' -
.I TOTAL 1.86E-04 3.72E-05 2.23E-04 3.72E-OS DE-131 4.61E-05 5.04E-07 4.66E-05 5.04E-07!
NOTE: Results shown above are corrected for any dilution. ( i l 9/20/89, Page 10.2.2.1.22 - 2 i
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y .- i: NEW HAMPSHIRE YANKEE 1 , SEABROOK STATION. 1989 ' GRADED EXERCISE 10.2 : CHEMISTRY ' D AT A 10.2.2 GAMMA: SPECTROSCOPY ' ANAYLSES
'10.2.2.2 CONTAINMENT. ATMOSPHERE
.j NOTE TO CONTROLLER INITI AL SAMPLE RESULTS ARE VALID UNTIL 09:00 AM y
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I. ! f ANNUAL' EXERCISE, Revision 2.0 t; ,. l I-GAMMA SPECTRUM ANALYSIS I CANBERRA.SPECTRAN-F V3.00 SOFTWARE . NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF
-SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 0700
. RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED- ERROR CORRECTED ERROR A'r-41 1.73E-12 2.67E-14 1.76E-12 2.67E-14 Kr-85 3.53E-12~ 4.42E-14 3.58E-12 4,42E-14 Xe-131m 5.32E-12 6.18E-14 5.38E-12 6.18E-14 Xe-133m 3.37E-11 4.73E-13 3.42E-11 4.73E-13 Xe-133 7.08E-10 8.20E-12 7.16E-10 8.20E-12 l Xe-135 2.09E-10 3.51E-12 2.13E-10 3.51E-12 i TOTAL 9.61E-10 1.23E-11 9.73E-10 1.23E-11 2
9/20/89, Page 10.2.2.2.1 l
L ANNUAL EXERCISE, Revision 2.0 : GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 0900 RADIONUCLIDES' ANALYSIS REPORT l ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Ar-41 1.73E-12 2.05E-14 1.75E-12 2.05E-14 Kr-85m 4.60E-10 7.20E-12 4.67E-10 7.20E-12 Kr-85. 1.15E-11 2.17E-13 1.18E-11 2.17E-13
-Kr-87 8.85E-10 1.50E-11 9.00E-10 1.50E-11 Kr-88 1.25E-09 1.31E-11 1.26E-09 1.31E-11 Xe-131m 1.74E-11 3.04E-13 1.78E-11 3.04E-13 Xe-133m 1.10E-10 1.65E-12 1.12E-10 1.65E-12 Xe-133 3.52E-09 6.29E-11 3.59E-09 6.29E-11 Xe-135 6.84E-10 6.91E-12 6.91E-10 6.91E-12 l
TOTAL 6.94E-09 1.07E-10 7.05E-09 1.07E-10 9/20/89, Page 10.2.2.2.2 _ __ ___J
ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE j GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 0915 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Ar-41 1.73E-12 2.48E-14 1.75E-12 2.48E-14 Kr-85m 4.60E-10 7.13E-12 4.67E-10 7.13E-12 Kr-85 1.15E-11 2.08E-13 1.18E-11 2.08E-13 Kr-87 9.11E-10 1.41E-11 9.25E-10 1.41E-11 Kr-88 1.25E-09 1.80E-11 1.27E-09 1.80E-11 Xe-131m 1.74E-11 1.99E-13 1.76E-11 1.99E-13 Xe-133m 1.10E-10 2.14E-12 1.13E-10 2.14E-12 Xe-133 3.52E-09 6.43E-11 3.59E-09 6.43E-11 Xe-135 6.84E-10 8.40E-12 6.93E-10 8.40E-12 l TOTAL 6.97E-09 1.15E-10 7.08E-09 1.15E-10 9/20/89, Page 10.2.2.2.3
i .. ANNUAL EXERCISE,> Revision.2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP. SHELF SAMPLE: SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 0930
' RADIONUCLIDES ANALYSIS REPORT
. ACTIVITY CONCENTRATION IN' uCi/cc NUCLIDE MEASURED ERROR CORRECTED- ERROR Ar-41 1.73E-12 3.08E-14 1.76E-12' 3.08E-14 Kr-85m -4.60E-10 5.58E-12 4.66E-10 5.58E-12 Kr-85 1.15E-11 1.68E-13 1.17E-11 1.68E-13 Kr 9.38E-10 1.35E-11' 9.52E-10 1.35E-11 Kr-88 1.25E-09 1.57E-11 1.26E-09 1.57E-11 Xe-131m 1.74E-11 1.97E-13 1.76E-11 1.97E-13 Xe-133m '1.10E-10 1.17E-12 1.12E-10 1.17E-12 Xe-133' 3.52E-09 5.62E-11 3.58E-09 5.62E-11
-Xe-135 6.84E-10 6.93E-12 6.91E-10 6.93E-12 I
TOTAL 6.99E-09 9.95E-11 7.09E-09 9.95E-11 9/20/89, Page 10.2.2.2.4 ,
ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 0945 (I T RADIONUCLIDES ANALYSIS REPORT j ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Ar-41 1.73E-12 2 76E-14 1.76E-12 2.76E-14 Kr-85m 4.60E-10 8.15E-12 4.68E-10 8.15E-12 Kr-85 1.15E-11 1.80E-13 1.17E-11 1.80E-13 Kr-87 9.66E-10 1.78E-11 9.63E-10 1.78E-11 Kr-88 1.25E-09 2.07E-11 1.27E-09 2.07E-11 Xe-131m 1.74E-11 3.15E-13 1.7dE-11 3.15E-13 Xe-133m 1.10E-10 1.80E-12 1.12E-10 1.80E-12 Xe-133 3.52E-09 4.70E-11 3.57E-09 4.70E-11 l Xe-135 6.84E-10 1.28E-11 6.97E-10 1.28E-11 l TOTAL 7.02E-09 1.09E-10 7.13E-09 1.09E-10 , 9 r. 9/20/89, Page 10.2.2.2.5 l.
ANNUAL EXERCISE, Revision 2.0 I GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10 0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1000 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc l l NUCLIDE MEASURED ERROR CORRECTED ERROR l ! Ar-41 1.73E-12 1.80E-14 1.75E-12 1.80E-14 Kr-85m 4.60E-10 6.67E-12 4.67E-10 6.67E-12 L Kr-85 1.15E-11 1.50E-13 1.17E-11 1.50E-13 l Kr-87 9.94E-10 1.18E-11 1.01E-09 1.18E-11
- Kr-88 1.25E-09 2.04E-11 1.27E-09 2.04E-11 Xe-131m 1.74E-11 3.36E-13 1.78E-11 3.36E-13 Xe-133m 1.10E-10 1.64E-12 1.12E-10 1.64E-12 Xe-133 3.52E-09 4.05E-11 3.56E-09 4.05E-11 Xe-135 6.84E-10 7.08E-12 6.92E-10 7.08E-12 l
TOTAL 7.05E-09 8.86E-11 7.14E-09 8.86E-11 9/20/89, Tage 10.2.2.2.6
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' ANNUAL. EXERCISE,. Revision'2..O.
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i GAMMA SPECTRUM ANALYSIS i p . CANBERRA SPECTRAN-F..-V3.00 SOFTWARE { 1 NEW HAMPSHIRE YANKEE-CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY. DESCRIPTION:: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1015' RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION'IN uCi/cc NUCLIDE' MEASURED ERROR CORRECTED ERROR
' Ar-41 1.73E-12 2.88E-14 1.76E-12 2.88E-14
- Kr-85m 4.60E-10 5.99E-12 4.66E-10 5,99E-12 Kr-85 1.15E-11 2.18E-13 1.18E-11 2.18E-13' i Kr-87 1.02E-09. 1.23E-11 1.04E-09 1.28E-11
- Kr-881 1.25E-09 1.82E-11 1.27E-09 1.82E-11 Xe-131m l'.74E-11 2.26E-13 1.77E-11 2.26E-13 Xe-133m: 1.10E-10 1.87E-12 1.12E-10 1.87E-12 Xe-133 3.52E-09 6.23E-11 3.59E-09 6.23E-11 Xe-135 6.84E-10' 8.22E-12 6.93E-10 8.22E-12 l
TOTAL 7.08E-09 1.10E-10 .7.19E-09 1.10E-10 l l 9/20/89, Page 10.2.2.2.7 j
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' ANNUAL EXERCISE,-Revision 2.0 Va i
-GAMMA' SPECTRUM ANALYSIS-CANBERRA SPECTRAN-F'V3.00 SOFTWARE NEWLHAMPSHIRE YANKEE CHEMISTRY DEPARTMENT ')
- SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION:' TOP. SHELF.
SAMPLE SIZE: 10.0 CC VIAL q
- DATE COLLECTED ON: 9/27/89 AT 1030 l RADIONUCLIDES ANALYSIS REPORT l ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Ar-41 1.73E-12 3.29E-14 -1.76E 3.29E-14 Kr-85m 4.60E-10 8.52E-12 4.69E-10 8.52E-12 Kr-85 1.15E-11 2.08E-13 1.18E-11 2.08E-13 Kr-87. 1.05E-09. 1.18E-11 1. 07E -0 9 1.18E Kr-88 1.25E-09 1.44E-11 1.26E-09 1.44E-11 Xe-131m 1.74E-1] 3.17E-13 1.78E-11 3.17E-13 Xe-133m 1.10E-1C 1.60E-12 1.12E-10 1.60E-12 Xe-133 3.52E-09 5.94E 3.58E-09 5.94E-11 Xe-135- 6.84E-10 1.31E-11 6.98E-10 1.31E-11 l
TOTAL 7.11E-09 1.09E-10 7.22E-09 1.09E-10 l j i 9/20/89, Page 10.2.2.2.8 !
l ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL i DATE COLLECTED ON: 9/27/89 AT 1045 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Ar-41 1.73E-12 2.98E-14 1.76E-12 2.98E-14 Kr-85m 4.60E-10 6.09E-12 4.66E-10 6.09E-12 Kr-85 1.15E-11 1.44E-13 1.17E-11 1.44E-13 Kr-87 1.08E-09 1.64E-11 1.10E-09 1.64E-11 Kr-88 1.25E-09 2.50E-11 1.28E-09 2.50E-11 Xe-131m 1.74E-11 1.86E-13 1.76E-11 1.86E-13 Xe-133m 1.10E-10 1.44E-12 1.12E-10 1.44E-12 Xe-133 3.52E-09 4.49E-11 3.57E-09 4.49E-11 Xe-135 6.84E-10 1.23E-11 6.97E-10 1.23E-11 l TOTAL 7.14E-09 1.06E-10 7.25E-09 1.06E-10 l l i l 9/20/89, Page 10.2.2.2.9
.J ANNUAL EXERCISE. Revision 2.0 4
a GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE , NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON:-9/27/89 AT 1100 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 4.60E-10 7.22E-12 4.68E-10 7.22E-12 Kr-85 l'.15 E-11 2.20E-13 1.18E-11 2.20E-13 Kr-87 1.12E-09 1.45E-11 1.13E-09 1.45E-11 Kr-88 '1.25E-09 1.27E-11 1.26E-09 1.27Eo11 Xe-131m 1.74E-11 3.18E-13 1.7BE-11 3.18E Xe-133m 1.10E-10 1.68E-12 1.12E-10 1.68E-12
;Xe-133 3.52E-09 6.98E-11 3.59E-09 6.98E-11 Xe-135 6.84E-10 1.29E-11 6.97E-10 1.29E-11 TOTAL 7.18E-09 1.19E-10 7.30E-09 1.19E-10 i
i I 9/20/89, Page 10.2.2.2.10
ANNUAL EXERCISE, Revision 2.0 L GAMMA SPECTRUM ANALYSIS , CANBERRA SPECTRAN-F V3.00 SOFTWARE p. NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT I SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP' SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1115 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 2.98E-09' 3.33E-11 3.01E-09 3.33E-11 Kr-85 7.47E-11 1.24E-12 7.59E-11 1.24E-12 l l Kr-87 5.72E-09 1.11E-10 5.84E-09 1.11E-10 Kr-88 8.07E-09 1.25E-10 8.19E-09 1.25E-10 Xe-131m 1.13E-10 1.93E-12 1.15E-10 1.93E-12 Xe-133m 7.14E-10 1.36E-11 7.28E-10 1.36E-11 Xe-133 2.28E-08 4.15E-10 2.32E-08 4.15E-10 Xe-135 4.43E-09 7.78E-11 4.50E-09 7.78E-11 l TOTAL 4.49E-08 7.78E-10 4.57E-08 7.78E-10 1 9/20/89, Page 10.2.2.2.11
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(' ' l l ,ANNUALLEXERCISE, Rev"ision 2.0; ; g-I id GAMMA SPECTRUM ANALYSIG CANBERRA SPECTRAN-F V3.00, SOFTWARE . u? : NEW HAMPSHIRE YANKEE CHEMISTRY-DEPARTMENT SAMPLE DESCRIPTION:' CONTAINMENT AIR SAMPLE l GEOMETRY DESCRIPTION: . TOP SHELF. j SAMPLE SIZE:.10.0 CC VIAL DATE COLLECTED'ON* 9/27/89-AT 1130 RADIONUCLIDES ANALYSIS-REPCRT f ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED- ERROR CORRECTED ERROR Kr-85m' '4.38E-09' .8.44E-11 4.47E-09 8.44E-11
- Kr-85 :1.10E-10 1.46E-12 1.11E-10 1.46E-12
--E =Kr 8.43E-09 1.61E-10 8.59E-09 1.61E-10 Kr-88. 11.19E-08. 2.23E-10 1.21E-08 2.23E-10 Xe-131m 1.66E-10' 2.65E-12 1.69E-10 2.65E-12 Xe-133m 1.05E-09 1.24E 1.06E-09 1~.24E-11
' Xe-133 3.35E-08' 5.17E 3.41E-08 .5.17E-10 Xe-135: 6 . 5 2 E-0 9 -- 1.28E-10 6.64E-09 1.28E-10 l
. TOTAL, ~6.61E-08 '1.13E-09 6.72E-08 1.13E-09
< { < 1 t 9/20/89, Page 10.2.2.2.12 - - _ _ = - _ - - _ - _ - _ - - - _ - _ _ _
'I l
ANNUAL-EXERCISE, Revision 2.0 #
)
l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1145 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 5.47E-09 8.43E-11 5.56E-09 8.43E-11 Kr-85 1.37E-10 2.34E-12 1.40E-10 2.34E-12 Kr-87 1.05E-08 1.62E-10 1.07E-08 1.62E-10 Kr-88 1.48E-08 2.86E-10 1.51E-08 2.86E-10 Xe-131m 2.08E-10 4.10E-12 2.12E-10 4.10E-12 Xe-133m 1.31E-09 2.08E-11 1.33E-09 2.08E-11 Xe-133 4.19E-08 6.07E-10 4.25E-08 6.07E-10 Xe-135 8.14E-09 1.38E-10 8.28E-09 1.38E-10 l TOTAL 8.26E-08 1.30E-09 8.39E-08 1.30E-09 1 9/20/89, Page 10.2.2.2.13 I l
pt b . l d "i ANNUAL EXERCISE, Revision 2.0 h j
].
GAMMA' SPECTRUM ANALYSIS 1 l .: CANBERRA SPECTRAN-F V3.00 SOFTWARE ' J NEW HAMPSHIRE' YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE l GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL lDATE; COLLECTED ON: 9/27/89-AT.1200
' RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m- 6.51E-09 1.13E-10 6.63E-09 1.13E-10 Kr-85: ~1.63E-10 2.94E-12 1.66E-10 2.94E-12 Kr-87 1.25E-08 2.43E-10 1.2BE-08 2.43E-10 Kr-88 1.'77E-08 2.45E-10 1.79E-08 2.45E-10
.Xe-131m 2.47E-10 4.64E-12 2.52E-10 4.64E-12 Xe-133m 1.56E-09 1.88E-11 1.58E-09 1.88E-11 I Xe-133 4.99E-08 6.23E-10 15.05E-08 6.23E-10
'Xe-135 9.69E-09 1.43E-10 9.83E-09 1.43E-10 ;
l TOTAL 9.82E-08 1.39E-09 9.96E-08 1.39E-09 l i H 9/20/89, Page 10.2.2.2.14
/ .
i i ANNUAL EXERCISE',fRevision.2.0 GAMMA' SPECTRUM ANALYSIS-
.j d
CANBERRA =SPECTRAN-F V3.00 SOFTWARE . 1 1 NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE' GEOMETRY DESCRIPTION: TOP SHELF
-SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: .9/27/89 AT 1215 RADIONUCLIDES ANALYSIS REPORT ,
1 ACTIVITY' CONCENTRATION IN' uCi/cc NUCLIDE MEASURED ' ERROR CORRECTED ERROR Kr-85m 7;50E-09 l'.14E-10 7.62E-09 1.14E-10 Kr-85 1.88E-10 3.29E 1.92E-10 3.29E-12 Kr-87 1.44E-08 2.14E-10 1.46E-08 2.14E-10 Kr- 1- 2.03E-08 3.37E-10 2.07E-08 '3.37E-10 Xe-131m 2.84E-10 5.30E-12. 2.90E-10 5.30E-12 Xe-133m 1.80E-09 2.38E-11 1.82E-09 2.38E-11 Xe-133 5.74E-08 7.49E-10 .5.82E-08 7.49E-10 Xe-135 1.12E-08 1.57E-10 1.13E-08 1.57E-10 l-TOTAL 1.13E-07 1.60E-09 1.15E-07 1.60E-09 l
~
i r 9/20/89, Page 10.2.2.2.15 m
l l l ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM' ANALYSIS {
. CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1230 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 8.45E-09 1.33E-10 8.59E-09 1.33E-10 Kr-85 2.12E-10 2.31E-12 2.14E-10 2.31E-12 Kr-87 1.63E-08 2.82E-10 1.65E-08 2.82E-10 Kr-88 2.29E-08 3.07E-10 2.32E-08 3.07E-10 Xe-131m 3.20E-10 6.14E-12 3.27E-10 6.14E-12 Xe-133m 2.03E-09 3.04E-11 2.06E-09 3.04E-11 Xe-133 6.47E-08 1.05E-09 6.58E-08 1.05E-09 Xe-135 1.26E-08 2.01E-10 1.28E-08 2.01E-10 l
TOTAL 1.27E-07 2.01E-09 1.29E-07 2.01E-09 9/20/89, Page 10.2.2.2.16
l ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS ' CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT , SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF l SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1245 RADIONUCLIDES ANALYSIS REPORT , ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 9.37E-09 1.48E-10 9.51E-09 1.48E-10 - Kr-85 2.35E-10 3.08E-12 2.38E-10 3.08E-12 . Kr-87 1.80E-08 2.33E-10 1.82E-08 2.33E-10 l Kr-88 2.54E-08 3.87E-10 2.58E-08 3.87E-10 Xe-131m 3.55E-10 4.29E-12 3.59E-10 4.29E-12 l Xe-133m 2.25E-09 4.45E-11 2.29E-09 4.45E-11 Xe-133 7.17E-08 1.41E-09 7.31E-08 1.41E-09 Xe-135 1.39E-08 2.13E-10 1.41E-08 2.13E-10 l TOTAL 1.41E-07 2.45E-09 1.44E-07 2.45E-09 l 6 9/20/89, Page 10.2.2.2.17
ANNUAL EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1300 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85n 1.02E-08 1.46E-10 1.04E-08 1.46E-10 Kr-85 2.57E-10 3.80E-12 2.61E-10 3.80E-12 Kr-87 1.97E-0B 3.66E-10 2.01E-08 3.66E-10 Kr-88 2.78E-08 3.20E-10 2.81E-08 3.20E-10 Xe-131m 3.88E-10 6.16E-12 3.95E-10 6.16E-12 Xe-133m 2.46E-09 4.62E-11 2.50E-09 4.62E-11 Xe-133 7.84E-08 1.45E-09 7.99E-08 1.45E-09 Xe-135 1.52E-08 2.39E-10 1.55E-08 2.39E-10 l TOTAL 1.54E-07 2.58E-09 1.57E-07 2.58E-09 9/20/89, Page 10.2.2.2.18
1 ANNUAL EXERCISE,JRevision 2.0
; GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE ,
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1315 RADIONUCLIDES ANALYSIS REPORT < l I ACTIVITY CONCENTRATION IN uCi/cc
- NUCLIDE MEASURED ERROR CORRECTED ERROR i
Kr-85m 1.96E-08 2.20E-10 1.98E-08 2.20E-10 Kr-85 e 4.92E-10 8.10E-12 5.00E-10 8.10E-12 Kr-87 3.77E-08 5.05E-10 3.82E-08 5.05E-10 Kr-88. 5.31E-08 5.85E-10 5.37E-08 5.85E-10 g Xe-131m 7.43E-10 7.94E-12 7'.51E-10 7.94E-12
. Xe-133m 4.70E-09 9.29E-11 4.79E-09 9.29E-11 l Xe-133 1.50E-07 1.70E-09' 1.52E-07 1.70E-09 Xe-135 2.91E-08 5.29E-10 2.97E-08 5.29E-10' TOTAL 2.96E-07 3.655-09 2.99E-07 3.65E-09 9/20/89, Page 10.2.2.2.19
x , t, i. {'.
. ANNUAL' EXERCISE, Ravision 2.0 y
' GAMMA' SPECTRUM ANALYSIS
' CANBERRA-SPECTRAN-F V3.00 SOFTWARE .
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT.
' SAMPLE DESCRIPTION: CONTAINMENT AIR. SAMPLE GEOMETRY DESCRIPTION: TOP ~ SHELF SAMPLE SIZE: 10 0 CC VIAL-DATE COLLECTED ON:-9/27/89 AT 1330 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc i
NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 2.89E-08 4.35E-10 2.93E-08 4.35E-10 Kr-85 7.24E-10 1.16E-11 7.36E-10 1.16E-11 14 Kr '5.55E-08 7.13E-10 5.62E-08 7.13E-10 Kr-88 7.82E-08 1.52E 7.98E-08 1.52E-09 Xe-131m 1.09E-09 1.54E-11 1.11E-09 1.54E-11 Xe-133m 6.93E-09 8.85E-11 7.01E-09 8.85E-11 Xe-133 2.21E-07 2.42E-09 2.23E-07 2.42E-09 Xe-135 4.29E-08 5.30E-10. '4.35E-08 5.30E-10 l TOTAL' 4.35E-07 5.74E-09 4.41E-07 5.74E-09 L , i n 1 l l 9/20/89, Page 10.2.2.2.20 l t-
}_qu uj. .I ANNUAL EXERCISE, Revision 2.0 L ( '.
~ GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F-V3.00 SOFTWARE ,\
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE-DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1345 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR l Kr-85m 3.87E-08 4.20E-10 3.91E-08 4.20E-10 Kr-85 9.70E-10 9.79E-12 9.80E-10 9.79E-12 Kr-87 7.44E-08 7.54E-10 7.51E-08 7.54E-10 Kr-88 1.05E-07 1.26E-09 1.06E-07 1.26E-09 Xe-131m 1.47E-09 2.46E-11 1.49E-09 2.46E-11 Xe-133m 9.28E-09 1.29E-10 9.41E-09 1.29E-10 Xe-133 2.96E-07 4.08E-09 3.00E-07 4.08E-09 Xe-135 , 5.75E-08 9.81E-10 5.85E-08 9.81E-10 l TOTAL 5.83E-07 7.66E-09 5.91E-07 7.66E-09 9/20/89, Page 10.2.2.2.21 l l
j i
- ANNUAL EXERCISE, Revision 2.0 l
GAMMA SPECTRUM ANALYSIS CANBERRA.SPECTRAN-F V3.00 SOFTWARE . NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT' I SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL
'DATE COLLECTED ON: 9/27/89 AT 1400 RADIONUCLIDES ANALYSIS REPORT 1 1
' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR !
Kr-85m 4.58E-08 6.32E-10 4.64E-08 6.32E-10 Kr-85 1.15E-09 2.24E-11 1.17E-09 2.24E-11 Kr-87 8.80E-08 1.53E-09 8.96E-08 1.53E-09 o Kr-88 1.24E-07 1.63E-09 1.26E-07 1.63E-09 Xe-131m 1.74E-09 2.50E-11 1.76E-09 2.50E-11 Xe-133m 1.10E-08 1.76E-10 1.12E-08 1.76E-10 Xe-133 3.50E-07 3.57E-09 3.54E-07 3.57E Xe-135 6.81E-08 1.05E-09 6.91E-08 1.05E-09 l ' TOTAL 6.90E-07 8.64E-09 6.99E-07 8.64E-09 l 9/20/89, Page 10.2.2.2.22 ; l
s c.- ' ANNUAL L EXERCISE,.RevisionT2.0*
.1 U GAMMA SPECTRUM ANALYSIS LCANBERRA SPECTRAN-F'V3.00-SOFTWARE
' NEW' HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT-
;t
.l
-4 SAMPLE'DESCRIPT.ON: CONTAINMENT AIR SAMPLE.
' GEOMETRY DESCRIPTION:. TOP SHELF
- SAMPLE SIZE: -10.0.CC "IAL DATE' COLLECTED ON: 1, .7/89 AT 1415
. RADIONUCLIDES ANALYSIS REPORT
~ ACTIVITY CONCENTRATION IN uCi/cc
- NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 5'.05E-08I- 9.5EE-10 5.15E-08 9.55E-10 Kr-85: 1.27E-09 2.32E-11 1.29E 2.32E-11 Kr-87: 9'71E-08
. 1.75E-09 9.89E-08 '1.75E-09 Kr 1.37E-07 1.54E-09 1.38E-07 1.54E-09 Xe-131m- 1.91E-09 2.73E-11 1.94E-09 2.73E-11 Xe-133m 1.21E-08 2.01E-10 1.23E-08 2.01E-10 Xe-133 3.87E-07 .5.19E-09 3.92E-07 5.19E-09 Xe-135. 7.51E-08 1.10E-09 7.62E-08 1.10E-09 l j
-TOTAL- ~7.62E-07 1.08E .7.72E-07 1.08E-08 .
I 1
'1 l
]
1 l l :: l l'. 9/20/89, Page 10.2.2.2.23 1 __ _ ui:_ _ _ _ __ _ ._
ANNUAL EXERCISE, Revision 2.0 , GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTIO.S: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1430 I RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 5.51E-08 5.66E-10 5.57E-08 5.66E-10 Kr-85 1.38E-09 1.50E-11 1.40E-09 1.50E-11 Kr-87 1.06E-07 1.90E-09 1.08E-07 1.90E-09 Kr-88 1.49E-07 1.83E-09 1.51E-07 1.83E-09 Xe-131m 2.09E-09 4.14E-11 2.13E-09 4.14E-11 Xe-133m 1.32E-08 2.56E-10 1.35E-08 2.56E-10 Xe-133 4.22E-07 7.13E-09 4.29E-07 7.13E-09 Xe-135 8.20E-08 1.60E-09 8.36E-08 1.60E-09 l TOTAL 8.31E-07 1.33E-08 0.45E-07 1.33E-08 i 9/20/89, Page 10.2.2.2.24
ANNUAL EXERCISE, Revision 2.0 l GAMMA SPECTRUM ANALYSIS
' CANBERRA SPECTRAN-F V3.00 SOFTWARE ,
i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT J SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL
-DATE COLLECTED ON: 9/27/89 AT 1445 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc
.NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 5.97E-08 6.60E-10 6.03E-08 6.60E-10 Kr-85 1.50E-09 2.66E-11 1.52E-09 2.66E-11 Kr-87. 1.15E-07 2.28E-09 1.17E-07 2.28E-09 Kr-88 1.62E-07 2.14E-09 1.64E-07 ?. 14E-09 Xe-131m 2.26E-09 2.33E-11 2.29E-09 2.33E-11
'Xe-133m 1.43E-08 1.74E-10 1.45E-08 1.74E-10 Xe-133 4.57E-07 4.62E-09 4.61E-07 4.62E-0?
Xe-135 8.87E-08 9.31E-10 8.97E-08 9.31E-10 l-TOTAL 9.00E-07 1.09E-08 9.11E-07 1.09E-08 1 1 9/20/89, Page 10.2.2.2.25
.y
. ANNUAL-EXERCISE,'Ravision 2.0
. GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE- ,
NEW HAMPSHIRE-YANKEE CHEMISTRY DEPARTMENT
. SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE GEOMETRY DESCRIPTION: TOP SHELF
. SAMPLE SIZE: '10.0 CC VIAL
_DATE COLLECTED ON: 9/27/89 AT 1500 RADIONUCLIDES ANALYSIS REPORT
. ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m 6.41E-08 1.05E-09 6.51E-08 1.05E-09 Kr-85 1.61E-09 2.56E-11 1.63E-09 2.56E-11 Kr-87. 1.23E-07 .1.87E-09 1.25E-07 1.87E-09 Kr-88 1.74E-07 3.24E-09 1.77E-07. 3.24E-09 Xe-131m .2.43E-09 3.36E-11 2.46E-09 3.36E-11
'Xe-133m
.1.54E-08 2.77E-10 1.57E-08 2.77E-10 Xe-133 4.91E-07 5.24E-09 4.96E-07 5.24E-09 Xe-135 9.53E 08 9.58E-10 9.63E-08 9.58E-10 l
. TOTAL 9.66E-07 1.27E-08 9.79E-07 1.27E-08 l
I I i 9/20/89, Page 10.2.2.2.26
1 kr ij < 1 1
' ;']
^ , ,
ANNUAL EXERCISE,; Revision 12.0 j 1 1 l
; -GAMMA SPECTRUM-ANALYSIS CANBERRA:SPECTRAN-F.V3.00 SOFTWARE-i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT.
((
^'
s SAMPLE DESCRIPTION:' CONTAINMENT AIR. SAMPLE GEOMETRY-DESCRIPTION: TOP SHELF
-SAMPLE SIZE: ~10.0 CC VIAL g 'DATE COLLECTED ON: 9/27/89 AT 1515- a RADIONUCLIDES' ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE . MEASURED ERROR CORRECTED ERROR
~Kr-85m 6.84E-08 -1.10E-09 6.95E-08 1.10E-09 Kr-85 '1.72E 3.31E-11. 1.75E-09' 3.31E-11 Kr-87 '1.32E-07 -2.23E-09 1.34E-07 2.23E-09
- l. .Kr-88 1.85E-07 2.77E-09 1.88E-07 2.77E-09
'Xe-131m 2.59E-09 3.35E-11 2.63E-09 3.35E-11 Xe-133m 1.64E-08 3.03E-10 1.67E-08 3.03E-10 Xe-133 '5.24E-07 --6.24E-09 5.'30E-07 6.24E-09'
.Xe-135 1.02E-07 1.35E-09 -1.03E-07 1.35E l TOTAL 1.03E-06 1.41E-08 1.05E-06. 1.41E-08 I:
L 1 l l V 1 9/20/89, Page 10.2.2.2.27 p
t L L:: - - - - _ _ _ . - - - - _ _ _ _ _ _ _ - _ _ _ - - _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ w
V V . ANNUAL ~ EXERCISE, Revision 2.0 GAMMA SPECTRUM ANALYSIS CANBERRA'SPECTRAN-F V3.00 SOFTWARE , NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT ~ r SAMPLE DESCRIPTION: CONTAINMENT AIR ~ SAMPLE-GEOMETRY DESCRIPTION: TOP SHELF SAMPLE-SIZE: .10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1530 RADIONUCLIDES' ANALYSIS REPORT
' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr -85m :7.27E-08 9.34E-10 7.36E-08 9.34E-10 Kr-85 -1.82E-09. 2.60E-11 1.85E-09 2.60E-11 Kr-87 1.40E-07. 2.45E-09 1.42E-07 2.45E-09 Kr-88 1.97E 3.66E-09 2.01E-07 3.66E-09 Xe-131m 2.76E-09 4'.21E-11 2.80E-09 4.21E-11 Xe-133m, 1.74E-08 2.82E-10 1.77E-08 2.82E-10 Xe-133- 5.56E-07 7.77E-09 5.64E-07 7.77E-09 i Xe-135 1.08E-07 1.49E-09 -1.10E-07 1.49E-09 l
TOTAL 1.10E-06 1.67E-08 1.11E-06 1.67E-08 9/20/89, Page 10.2.2.2.28 __-. -__-______--__-___a
.1
$8j ANNUAL EXERCISE, Revision 2.0 14 o
j%j
.e w
it .jJ,7 l . k GAMMA SPECTRUM ANALYSIS '; .}*'.i
'.t. s:!r{' .
CANBERRA SPECTRAN-F V3.00 SOFTWARE I.iI "i i7
1,.
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT :~.. OI
.s-l' SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE i. 9.:1 GEOMETRY DESCRIPTION: TOP SHELF p <y ..
SAMPLE. SIZE: 10.0 CC VIAL h.El DATE COLLECTED ON: 9/27/89 AT 1545 Y y
?,y. ,.
RADIONUCLIDES ANALYSIS REPORT [fr J .: ACTIVITY CONCENTRATION IN uCi/cc [4 9
%n, -
4, te. NUCLIDE MEASURED ERROR CORRECTED ERROR 9) . y-j [ Kr-85m 7.68E-08 1.13E-09 7.80E-08 1.13E-09 j ," Kr-85 1.93E-09 2.70E-11 1.96E-09 2.70E-11 -Q . Kr-87 1.48E-07 2.91E-09 1.51E-07 2.91E-09 M ,'.1 Kr-88 2.08E-07 2.51E-09 2.11E-07 2.51E-09 .:;
..p.-
Xe-131m 2.91E-09 4.36E-11 2.96E-09 4.36E-11 ,., ;.i. ' Xe-133m 1.84E-08 3.66E-10 1.88E-08 3.66E-10 . 2
'g. )
Xe-133 5.88E-07 7.32E-09 5.96E-07 7.32E-09 .? Xe-135 1.14E-07 1.77E-09 1.16E-07 1.77E-09
".?/
TOTAL 1.16E-06 1.61E-08 1.17E-06 1.61E-08 ~ 3._.*
- } g A :,
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U,g - ,
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v-9/20/89, Page 10.2.2.2.29
r, p ANNUAL EXERCISE, Rsvision 2.0 F GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE
.NEW HAMPSHIRE YANKEE CHEMISTRY ~ DEPARTMENT l
SAMPLE DESCRIPTION: CONTAINMENT AIR SAMPLE l GEOMETRY. DESCRIPTION: TOP SHELF SAMPLE SIZE: 10.0 CC VIAL DATE COLLECTED ON: 9/27/89 AT 1600 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-85m~ 8.09E-08 1.16E-09 8.21E-08 1.16E-09 Kr-85 -2.03E-09 2.86E-11 2.06E-09 2.86E-11 Kr-87 1.56E-07 2.94E-09 1.59E-07 2.94E-09
-Kr-88 2.19E-07 2.27E-09 2.22E-07 2.27E-09 i Xe-131m 3.07E-09 4.18E-11 3.11E-09 4.18E-11 Xe-133m 1.94E-08 2.76E-10 1.97E-08 2.76E-10 Xe-133- 6.20E-07 1.12E-08 6.31E-07 1.12E-08 Xe-135 1.20E-07 2.09E-09 1.22E-07 2.09E-09 l
TOTAL 1.22E-06 2.00E-08 1.24E-06 2.00E-08 a 9/20/89, Page 10.2.2.2.30
7 NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 4 10.2 CHEMISTAY DAT A 10.2.2 GAMMA SPECTROSCOPY ANAYLSES E 10.2.2.3 WRGM FILTERS
m,..,. . ., . -
- u ;,,'
, -iil1 0 :.
s l .3. . NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 10.2 CWEMISTAV D AT A 10.2.2 GAMMA SPECTROSCOPY ANAYLSES 10,2.2.3 WRGM FILTERS. 1 NOTE TO CONTROLLER INITI AL SAMPLE RESULTS ARE VALID UNTIL 09 00 AM l l.
;l
- _ _ _ _ . - _ - - _ - - . - J
l ANNUAL EXERCISE, Revision 2.0 l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM GAS GEOMETRY DESCRIPTION: TOP SHELF SAMPLE SIZE: WRGM GAS DATE COLLECTED ON: 9/27/89 AT 0700 - 1100 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Kr-87 1.56E-11 2.23E-13 1.58E-11 2.23E-13 Kr-88 2.19E-11 3.90E-13 2.23E-11 3.90E-13 Xe-133 6.20E-11 1.02E-12 6.30E-11 1.02E-12 l Xe-135 1.20E-11 1.99E-13 1.22E-11 1.99E-13 TOTAL 1.12E-10 1.83E-12 1.13E-10 1.83E-12 1 9/20/89, Page 10.2.2.3.0
3 i I) i. , ANNUAL EXERCISE, Revision'1.0 I li GAMMA' SPECTRUM ANALYSIS f l 1
'k CANBERRA SPECTRAN-F V3.00 SOFTWARE j l
NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT ! SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE N7"": 1.71E+07CC DATE COLLECTED ON: 9/27/89 AT 0700 RADIONUCLIDES ANALYSIS' REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 2.28E-12 4.57E-13 2.74E-12 4.57E-13' l TOTAL 2.28E-12 4.57E-13 2.74E-12 4.57E-13l 4 9/20/89, Page 10.2.2.3.1
1 ANNUAL EXERCISE, Revision 1.0 i GAMMA SPECTRUM ANALYSIS l
'l CANBERRA SPECTRAN-F V3.00 SOFTWARE i
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT f SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 1.71E+07CC DATE COLLECTED ON: 9/27/89 AT 0700 RADIONUCLIDES ANALYSIS REPORT ' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 3.31E-12 6.62E-13 3.97E-12 6.62E-13 Cs-137 1.66E-12 3.33E-13 1.99E-12 3.33E-13 TOTAL 4.96E-12 9.95E-13 5.96E-12 9.95E-13 i l t' l 9/20/89, Page 10.2.2.3.1 - 2
ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE , 1 NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED I SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1100 RACIONUCLIDE ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc 4 NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 2.28E-12 4.58E-13 2.74E-12 4.58E-13' i TOTAL 2.28E-12 4.58E-13 2.74E-12 4.58E 4 I 9/20/89, Page 10.2.2.3.2
r
-i ANNUAL EXERCISE, Revision 1.0 i
GAMMA SPECTRUM ANALYSIS j g; ;"-'
. -{
CANBERRA SPECTRAN-F V3.00 SOFTWARE , 9 NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT
-SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY. DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1100 RADIONUCLIDES' ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR
'Cs-134 3.39E-12 6.78E-13 4.06E-12 6.78E-13 Cs-137 1.69E-12 3.40E-13 2.03E-12 3.40E-13 TOTAL 5.08E-12 1.02E-12 6.10E-12 1.02E-12 i,
l l l-9/20/89, Page 10.2.2.3.2 - 2 { L _ _ - --_ -- - ----___------_-------------- - - - -- - -. - -
ANNUAL EXERCISE,iRevision 1.0 GAMMA SPECTRUM: ANALYSIS \ , j CANBERRA'SPECTRAN-F V3.00 SOFTWARE - l l NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT N, 'f SAMPLE DESCRIPTION: WRGM ' IODINE L GEOMETRY DESCRIPTION' FACE LOADED SAMPLE SIZE: 2.55E+04 CC-DATE COLLECTED ON: 9/27/89 AT 1115 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc . NUCLIDE MEASURED ERROR CORRECTED ERROR. { i I-131 2.95E-12 5.93E-13 3.55E-12' 5.93E I-132- 4.28E-12 8.59E-13. 5.14E-12 8.59E-13 I-133 6.04E-12 1.21E-12 .7.25E 1.21E-12 I-134 6.61E-12 1.32E-12 7.94E-12 1.32E-12 I-135 5.~63E-12 '1.13E-12 6.76E-12 1.13E-12:
-TOTAL 2.55E-11 5.12E-12 3.06E-11 5.12E-12 l
9/20/89, Page 10.2.2.3.3
, , .)
l r).,$ \ ? s
, q<
p . 9:; '. ANNUAL. EXERCISE,: Revision'1.0'
~
+
\; ;; 3, ki 'r I l GAMMA SPECTRUM ANALYSIS. CANBERRA'SPECTRAN-F V3.00 SOFTWARE' .
'NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT L
l SAMPLE' DESCRIPTION: WRGM, PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT-'1115 RADIONUCLIDES ANALYSIS REPORT
. ACTIVITY CONCENTRATION IN .uCi/cc NUCLIDE MEASURED ERROR CORRLCTED ERROR Cs-134 3.35E-13 6.72E-14 4.02E-13 '6.72E-14.
,Cs-137. l'.88E-13 3.7.7E-14 2'.25E-13 3.77E-14
. TOTAL 5.23E-13 1.'05E-13. 6.27E-13 1.05E-13 I
1 l l 9/20/89, Page 10.2.2.3.3 - 2 _ _ _ _ = _ ______ _ _______ _ _ _ -
l l i ANNUAL EXERCISE, Revision 1.0 j 1 4 GAMMA SPECTRUM ANALYSIS l CANBERRA SPECTRAN-F V3.00 SOFTWARE , j NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E F04 CC DATE COLLECTED ON: 9/27/89 AT 1130 RADIONUCLIDES ANALYSIS REPORT ACTIVITY. CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 6.52E-12 1.31E-12 7.83E-12 1.31E-12' I-132 9.45E-12 1.90E-12 1.13E-11 1.90E-12 I-133 1.33E-11 2.67E-12 1.60E-11 2.67E-12 I-134 1.46E-11 2.93E-12 1.75E-11 2.93E-12 I-135 1.24E-11 2.49E-12 1.49E-11 2.49E-12: TOTAL 5.63E-11 1.13E-11 6.76E-11 1.13E-11 l l l l l l l l l l 9/20/89, Page 10.2.2.3.A. j 1 L____---
ANNUAL EXERCISE, Revision 1.C , 1 l 1 GAMMA SPECTRUM ANALYSIS. CANBERRA SPECTRAN-F V3.00 SOFTWARE i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT j SAMPLE DESCRIPTION: WRGM PARTICULATE l
)
GEOMETRY DESCRIPTION: FACE LOADED l SAMPLE SIZE: 2.55E+04 CC i DATE COLLECTED ON: 9/27/89 AT 1130 RADIONUCLIDES ANALYSIS REPORT , ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 3.35E-13 6.71E-14 4.02E-13 6.71E-14 Cs-137 1.90E-13 3.80E-14 2.28E-13 3.80E-14 TOTAL 5.25E-13 1.05E-13 6.30E-13 1.05E-13
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9/20/89, Page 10.2.2.3.4 -2
ANNUAL EXERCISE, Revision 1.0 1 k , i
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I GAMMA SPECTRUM ANALYSIS !
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CANBERRA'SPECTRAN-F V3.00 SOFTWARE , NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE i GEOMETRY DESCRIPTION: FACE LOADED
. SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1145 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 1.09E-11 2.18E-12 1.30E-11 2.18E-12:
1-132 1.57E-11 3.16E-12 1.89E-11 3.16E-12. . I-133 2.22E-11 4.46E-12 2 67E-11 4.46E-12: l I-134 2.43E-11 4.88E-12 2.92E-11 4.88E-12. I-135 2.07E-11 4.16E-12 2.49E-11 4.16E-12' TOTAL 9.38E-11 1.88E-11 1.13E-10 1.88E-11
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9/20/89, Page 10.2.2.3.5 I
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ANNUAL EXERCISE, Revision 1.0 i GAMMA SPECTRUM ANALYSIS. CANBERRA SPECTRAN-F V3.00 SOFTWARE - NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT ' SAMPLE DESCRIPTION: WRGM PARTICULATE
' GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC
-DATE COLLECTED ON: 9/27/89 AT 1145 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc.
NUCLIDE MEASURED ERROR CORRECTED ERROR' Cs-134 3.38E 6.77E-14 4.06E-13 6.77E-14 Cs-137 2.06E-13 4.~13E-14 2.47E-13 4.13E-14 TOTAL 5.44E-13 1. 0 9 E-13.. 6.53E-13 1.09E-13 i l 5 I 9/20/89, Page 10.2.2.3.5 - 2 _ _ _ _ _ _ _ - _ _ - - - - - - - - - - - _ _ b
i ANNUAL EXERCISE, Rsvision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC 4 DATE COLLECTED ON: 9/27/89 AT 1200 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc ! NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 1.62E-11 3.24E-12 1.94E-11 3.24E-12! I-132 2.34E-11 4.70E-12 2.81E-11 4.70E-12 I-133 3.30E-11 6.63E-12 3.96E-11 6.63E-12. I-134 3.62E-11 7.26E-12 4.34E-11 7.26E-12; I-135 3.08E-11 6.18E-12 3.70E-11 6.18E-121 TOTAL 1.40E-10 2.80E-11 1.68E-10 2.80E-11 1 9/20/89, Page 10.2.2.3.6
1 I i ANNUAL EXERCISE, Revision 1.0 j p . (
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GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT j SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1200 I RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 3.42E-13 6.84E-14 4.10E-13 6.84E-14 Cs-137 2.25E-13 4.51E-14 2.70E-13 4.51E-14 TOTAL 5.67E-13 1.13E-13 6.80E-13 1.13E-13 i i 1 i 9/20/89, Page 10.2.2.3.6 - 2
ANNUAL EXERCISE, Revision 1.0 , GAMMA SPECTRUM ANALYSIS
-CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE. YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1215 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 2.23E-11 4.49E-12 2.68E-11 4.49E-12l I-132 3.24E-11 6.48E-12 3.88E-11 6.48E-12l
. I-133 4.56E-11 9.16E-12 5.48E-11 9. 6E-121 I-134 5.00E-11 1.00E-11 6.00E-11 1.00E-11' I-135 4.26E-11 8.53E-12 5.11E-11 8.53E-12 TOTAL 1.93E-10 3.87E-11 2.32E-10 3.87E-11
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9/20/89, Page 10.2.2.3.7
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' ANNUAL EXERCISE, Rsvision l'.0 -
1.
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GAMMA SPECTRUM ANALYSIS: CANBERRA-SPECTRAN-F V3.00 SOFTWARE ,
'I NEW HAMPSHIRE YANKEE CHEMISTRY' DEPARTMENT f
SAMPLE DESCRIPTION: WRGM PARTICULATE
. GEOMETRY DESCRIPTION: FACE LOADED
- ' SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1215 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION-IN. uCi/cc.
NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134- 3.46E-13 6.92E-14 4.15E-13 6.92E-14
. Cs-1~37 2.48E-13 4.97E-14 2.97E-13' 4.97E-14
- i. .
TOTAL- 5.93E-13 1.19E-13 '7.12E-13 1.19E-13 i l l l p 9/20/89, Page 10.2.2.3.7 - 2 l. L_-_-_-________-___------_______--__- - . _ - ._ _ . _ - . .
ANNUAL EXERCISE, Revision 1.0 i GAMMA SPECTRUM ANALYSIS CANBERI.A SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1230 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc l NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 2.93E-11 5.90E-12 3.52E-11 5.90E-12 I-132 4.25E-11 8.53E-12 5.10E-11 8.53E-12 I-133 6.00E-11 1.20E-11 7.20E-11 1.20E-11 I-134 6.57E-11 1.31E-11 7.89E-11 1.31E-11 I-135' 5.60E-11 1.12E-11 6.72E-11 1.12E-11, TOTAL 2.54E-10 5.08E-11 3.04E-10 5.08E-11! I t 9/20/89, Page 10.2.2.3.8
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L.. -ANNUAL EXERCISE,. Revision"1.0 ) h -i l' GAMMA SPECTF.UM' ANALYSIS 3 3 l CANBERRA SPECTRAN-F'V3.00 SOFTWARE NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE' DESCRIPTION: WRGM PARTICULATE
, GEOMETRY' DESCRIPTION:-FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON:-9/27/89 AT 1230' RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED . ERROR Cs-134 3.50E-13 7.04E-14 4.21E-13' 7.04E-14 Cs-137 '2.73E-13 5.48E-14 3.28E-13 5.48E-14
- TOTAL'. 6.23E-13 1.25E-13. 7.49E-13 l'.25E-13 l
i I 9/20/89, Page 10.2.2.3.8 - 2
p-3 43: ANNUAL EXERCISE, Revision l'.0- l GAMMA SPECTRUM' ANALYSIS.-- l- ,
. CANBERRA SPECTRAN-F'V3.00 SOFTWARE ,
NEW HAMSHIRE' YANKEE CHEMISTRYLDEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY' DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC -i DATE COLLECTED ON: 9/27/89 AT 1245-1 RADIONUCLIDES ANALYSIS REPORT 1 4 K , ACTIVITY CONCENTRATION IN uCi/cc
! NUCLIDE' MEASURED ERROR CORRECTED- ERROR I-131 3.72E-11 7.47E-12 4.46E-11 7.'47E-12 .
I-132 5.38E-11 1.08E-11 '6.46E-11 1.08E-11 l I-133 7.60E-11 1.52E-11 9.12E-11 1.52E-11' I-134 8.32E-11 1.67E-11 9.99E-11 1.67E-11 I-135- 7.09E-11 1.42E-11 8.51E-11 1.42E-11 TOTAL 3.21E-10 6.44E-11 3.85E-10 6.44E-11! l i l l l l 9/10/89, Page 10.2.2.3.9 ! l
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-ANNUAL EXERCISE,-Revision 1.0 GAMMA SPECTRUM ANALYSIS 4
' CANBERRA SPECTRAN-F V3.00 SOFTWARE -
1 NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE-GEOMETRY' DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89'AT 1245 RADIONUCLIDES. ANALYSIS REPORT ACTIVITY: CONCENTRATION IN uCi/cc NUCLIDE , MEASURED ERROR CORRECTED- ERROR Cs-134- 3.55E-13 -7.12E-14 4.27E-13 7.12E-14
- Cs-137 3.02E-13 6.05E-14 3.62E-13 6.05E-14 TOTAL 6.57E-13 1.32E-11 7.89E 1.32E-13.
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9/20/89, Page 10.2.2.3.9 - 2
v L. ANNUAL EXERCISE, Revision 1.0
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' GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F-V3.00 SOFTWARE ~I
- NEW HAMSHIRE. YANKEE' CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04fCC-
' DATE COLLECTED ON: 9/27/89 AT 1300 RADIONUCLIDES ANALYSIS REPORT
[. ' ACTIVITY CONCENTRATION IN uCi/cc
- NUCLIDE MEASURED ERROR CORRECTED ERROR
- I-131- 4.57E-11 9.16E-12 5.49E-11 9.16E-12 i - I-132 6.63E-11 1.33E-11 7.96E-11 1.33E-11
' I-133 -9.35E-11 1.88E-11 1.12E-10 1.88E-11 I-134 1.02E 2.05E-11 1.23E-10. 2.05E-11 I-135 8.72E-11 1.75E-11 1.05E-10 1.75E-11; TOTAL' 3.95E 7.92E-11 4.74E-10 7.92E-111 i
i l l l I i 9/20/89, Page 10.2.2.3.10
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ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1300 RADIONUCLIDES ANALYSIS REPORT I ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 3.61E-13 7.26E-14 4.34E-13 7.26E-14 Cs-137 3.33E-13 6.67E-14 3.99E-13 6.67E-14 TOTAL 6.94E-13 1.39E-13 8.33E-13 1.39E-13 i 9/20/89, Page 10.2.2.3.10 - 2
i ANNUAL EXERCISE, Revision 1.0 : i GAMMA SPECTRUM ANALYSIS
- CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION
- WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1315 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 9.72E-11 1.95E-11 1.17E-10 1.95E-11 I-132 1.41E-10 2.82E-11 1.69E-10 2.82E-11 l I-133 1.99E-10 3.98E-11 2.39E-10 3.98E-11 l I-134 2.18E-10 4.37E-11 2.61E-10 4.37E-11 I-135 1.85E-10 3.73E-11 2.23E-10 3.73E-11.
TOTAL 8.40E-10 1.69E-10 1.01E-09 1.69E-10 l 9/20/89, Page 10.2.2.3.11
L ANNUAL EXERCISE, Revision 1.0 l { l GAMMA SPECTRUM ANALYSIS ) CANBERRA SPECTRAN-F V3.00 SOFTWARE , NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1315 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 3.95E-13 7.92E-14 4.74E-13 7.92E-14 Cs-137 5.20E-13 1.04E-13 6.24E-13 1.04E-13 TOTAL 9.15E-13 1.83E-13 1.10E-12 1.03E-13 ( 9/20/89, Page 10.2.2.3.11 - 2
ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.03 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1330 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 1.57E-10 3.16E-11 1.89E-10 3.16E-11' l I-132 2.28E-10 4.58E-11 2.74E-10 4.58E-11 I-133 3.22E-10 6.44E-11 3.86E-10 '3 . 4 4 E-11. i I-134 3.53E-10 7.08E-11 4.23E-10 7.08E-11 l I-135 3.00E-10 6.02E-11 3.61E-10 6.02E-11: ) TOTAL 1.36E-09 2.73E-10 3.63E-09 2. 7 3 E-10i 9/20/89, Page 10.2.2.3.12
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' ANNUAL EXERCISE,' Revision'1.0 l i
'.4 b i GAMMA SPECTRUM ANALYSIS
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, -CANBERREL SPECTRAN-F V3.00 SOFTWARE -
NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT. L: ' SAMPLE-DESCRIPTION: WRGM PARTICULATE
~ GEOMETRY 1 DESCRIPTION: FACE, LOADED SAMPLE SIZE: 2.55E+04'.CC
!. .DATE COLLECTED ON: 9/27/89 AT 1330
~ RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED' ERROR CORRECTED ERROR-Cs-134 4.35E-13 8.72E-14 5.22E-13 8.72E-14--
Cs-137 7.40E-13 1.48E-13 8.88E-13 l'.48E Co-60 ~1.60E-13 3.21E-14 1.92E-13 3.21E-14 Co-58 1.25E-13 2.49E-14 1.50E-13 2.49E-14 Fe-59' 1.48E-13 2.96E-14 1.77E-13 2.96E-14 TOTAL 1.61E-12 3.22E-13 1.93E-12 3.22E-13 I l 9/20/89, Page 10.2.2.3.12 - 2 u-
1 1.
. ANNUAL EXERCISE, Revision'1.0 i
1 GAMMA SPECTRUM ANALYSIS 4 CANBERRA SPECTRAN-F V3.00 SOFTWARE - NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT
. SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1345 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN- uCi/cc
' NUCLIDE MEASURED ERROR . CORRECTED ERROR I-131. 2.30E-10 4.61E-11 2.76E-10 5.51E-11.
I-132 3.33E-10 6.69E-11 4.00E-10 7.98E-11~
- I-133 4.70E 9.45E-11 5.65E-10 1.13E-10 I-134 5.15E-10 1.03E-10 6.19E-10 1.23E-10 I-135 4.39E 8.81E-11 5.27E-10 1.05E-10i
. TOTAL 1.99E-09 3.99E-10 2.39E-09 4.76E-10 9/20/89, Page 10.2.2.3.13
ANNUAL EXERCISE, Rsvision 1.0 l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1345 RADIONUCLIDES ANALYSIS REPOS;T ACTIVITY CONCENTRATION IN ..Ci/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 4.83E-13 9.70E-14 5.80E-13 1.15E-13 Cs-137 3.18E-13 6.37E-14 3.82E-13 7.60E-14 Co-60 2.34E-13 4.69E-14 2.81E-13 5.61E-14 Co-58 1.82E-13 3.65E-14 2.19E-13 4.36E-14 Fe-59 2.16E-13 4.33E-14 2.59E-13 5.17E-14 TOTAL 1.43E-12 2.87E-13 1.72E-12 3.43E-13 9/20/89, Page 10.2.2.3.13 - 2
ANNUAL EXERCISE, Revision 1.0 L GAMMA SPECTRUM ANALYSIG CANBERRA SPECTRAN-F V3.00 SOFTWARE - NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT. SAMPLE DESCRIPTION: WRGM IODINE g -GEOMETRY DESCRIPTION: FACE LOADED L SAMPLE SIZE: 2.55E+04 CC L DATE COLLECTED ON: .9/27/89 AT 1400 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 2.95E-10 5.93E-11 3.54E-10 7.07E-11 I-132 4.28E-10 8.56E-12 5.13E-10 1.02E-10 I-133 6.03E-10 1.21E-10 7.24E-10 1.44E-10 L I-134 6.61E-10 1.32E-10 7.93E-10 1.58E-10 I-135 5.63E-10 1.13E-10 6.76E-10 1.34E-10. TOTAL 2.55E-09 5.11E-10 3.06E-09 6.10E-10} I 9/20/89, Page 10.2.2.3.14
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, ANNUAL EXERCISE, Revision 1.0' :
I i [ > GAMMA SPECTRUM ANALYSIS' i- . 1 CANBERRA SPECTRAN-F V3.00. SOFTWARE ,
.NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT.
SAMPLE DESCRIPTION: WRGM PARTICULATE
> GEOMETRY DESCRIPTION: FACE LOADED
~ SAMPLE SIZE:'2.55E+04 CC-
'DATE COLLECTED ON: 9/27/89 AT 1400 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc L.
i :- NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 5.26E-13 1.06E-13 6.32E-13 1.26E-13 Cs-137 3.61E-13 7.22E-14 4.33E-13 8.66E Co-60 3'.00E-13 6.03E-14 3.61E ~ 7.21E-14 Co-58 2.33E-13 4.68E-14 2.80E-13 5.58E-14 Fe-59' 2.77E-13 5.55E-14 3.32E-13 6.64E-14 TOTAL 1.70E-12 3.40E-13 2.04E-12 4.07E-13 p-9/20/89, Page 10.2.2.3.14 - 2 _j
ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1415 i RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 3.51E-10 7.03E-11 4.21E-10 8.39E-11. ! I-132 5.08E-10 1.02E-10 6.10E-10 1.22E-10 I-133 7.17E-10 1.44E-10 8.61E-10 1.72E-10 I-134 7.85E-10 1.58E-10 9.43E-10 1.88E-10 I-135 6.69E-10 1.34E-10 8.03E-10 1.60E-10 TOTAL 3.03E-09 6.08E-10 3.64E-09 7.26E-10l 1 9/20/89, Page 10.2.2.3.15 ) I _ _ _ _ _ _ _ _ _ _ _ - - - _ - - - _ _ - _ - - - - - - _ . - - - - _ - - - - _ _ - - - - - - - - - - - - - - - - - - - - - - _ - - - _ - - - - - -----------J
ANNUAL EXERCISE, Revision 1.0
)
I l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE 1 NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1415 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 S.63E-13 1.13E-13 6.76E-13 1.35E-13 Cs-137 3.98E-13 7.98E-14 4.78E-13 9.54E-14 Co-60 3.57E-13 7.15E-14 4.28E-13 8.54E-14 Co-58 2.77E-13 5.56E-14 3.33E-13 6.66E-14 Fe-59 3.29E-13 6.58E-14 3.95E-13 7.85E-14 TOTAL 1.92E-12 3.85E-13 2.31E-12 4.60E-13 I 9/20/89, Page 10.2.2.3.15 - 2
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,,- c kNNUAL" EXERCISE, RevisionT 1.0-
' GAMMA SPECTRUM l ANALYSIS-
-CANBERRA SPECTRAN-F'V3.00' SOFTWARE ,
NEW HAMSHIREl YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION:'WRGM IODINE-
-GEOMETRY DESCRIPTION: FACE LOADED-
-SAMPLE SIZE:'2.55E+04 CC DATE-COLLECTED ON: .9/27/89 AT 1430-RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN- uCi/cc.
.NUCLIDE MEASURED ERROR CORRECTED, ERROR' I-131. .'4.10E-10 8.22E-11 4.92E-10 8.22E-11.
-I-132- 5.94E-10 1.19E-10' -7.13E-10 1.19E-10.
I-133 8.38E-10 1.68E-10 11.01E-09 1.68E m LI-134 9.19E-10 1. 8 4 E- 10 ~-1.10E-09 1.84E-10: '
'I-135' 7.82E-10 1.57E-10 9.39E-10 1.57E-10li- l TOTAL 3.54E-09 7.11E-10 4.25E-09 7.11E-10
-1 l
l l 9/20/89, Page 10.2.2.3.16 l
' ANNUAL EXERCISE,-Revision 1.0 i GAMMA SPECTRUM ANALYSIS i
CANBERRA SPECTRAN-F V3.00' SOFTWARE . NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT ' SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC' DATE COLLECTED ON: 9/27/89 AT 1430 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I Cs-134 6.02E-13 1.21E-13 7.23E-13 1.21E-13 Cs-137 4.37E-13 8.78E-14 5.25E-13 8.78E-14 Co-60 4.17E-13 8.38E-14 5.01E-13 8.38E-14 Co-58 3.24E-13 6.50E-14 3.89E-13 6.50E-14 Fe-59 3.85E-13 7.70E-14 4.62E-13 7.70E-14 TOTAL 2.17E-12 4.34E-13 2.60E-12 4.34E-13 1 1 I 9/20/89, Page 10.2.2.3.16 - 2
l ( i j ANNUAL EXERCISE, Revision 1.0 i GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1445 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 4.73E-10 9.48E-11 5.68E-10 9.48E-11 I-132 6.86E-10 1.37E-10 8.23E-10 1.37E-10 I-133 9.68E-10 1.94E-10 1.16E-09 1.94E-10 I-134 1.06E-09 2.13E-10 1.27E-09 2.13E-10' I-135 9.03E-10 1.81E-10 1.08E-09 1.81E-106 1 TOTAL 4.09E-09 8.19E-10 4.91E-09 8.19E-10 I 9/20/89, Page 10.2.2.3.17
f; ANNUAL EXERCISE, Revision 1.0-GAMMA SPECTRUM ANALYSIS i-
. CANBERRA SPECTRAN-F V3.00 SOFTWARE -
l NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE' DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE:.2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1445 RADIONUCLIDES ANALYSIS REPORT
' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 6.44E-13 1.29E 7.74E-13 1.29E-13 Cs-137 4.79E-13 9.59E-14 5.75E-13 9.59E-14 Co-60 4.82E-13 9.67E-14 5.78E-13 9.67E-14 f Co-58 '3.74E-13 7.52E-14 4.50E-13 7.52E-14 Fe-59 4.44E-13 8.88E-14 5.33E-13 8.88E-14 TOTAL 2.42E-12 4.86E-13 2.91E-12 4.86E-13 9/20/89,'Page 10.2.2.3.17 - 2
r ANNUAL EXERCISE, Revision 1.0 l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE j GEOMETRY DESCRIPTION: FACE LOADED ' SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1500 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 5.40E-10 1.08E-10 6.49E-10 1.08E-10 I-132 7.83E-10 1.57E-10 9.40E-10 1.57E-10 I-133 1.10E-09 2.22E-10 1.33E-09 2.22E-10 I-134 1.21E-09 2.43E-10 1.45E-09 2.43E-10 I-135 1.03E-09 2.07E-10 1.24E-09 2.07E-10, TOTAL 4.67E-09 8.29E-10 4.96E-39 8.29E-10 I l 9/20/89, Page 10.2.2.3.18
1 ANNUAL EXERCISE, Revision 1.0 l GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE i NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED ! SAMPLE SIZE: 2.55E+04 CC ' DATE COLLECTED ON: 9/27/89 AT 1500 ( RADIONUCLIDES ANALYSIS REPORT 4 ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 6.89E-13 1.38E-13 8.27E-13 1.38E-13 Cs-137 5.23E-13 1.05E-13 6.28E-13 1.05E-13 Mn-54 1.02E-13 2.04E-14 1.22E-13 2.04E-14 Co-60 5.50E-13 1.10E-13 6.60E-13 1.10E-13 Co-58 4.27E-13 8.57E-14 5.13E-13 8.57E-14 Fe-59 5.06E-13 1.01E-13 6.08E-13 1.01E-13 TOTAL 2.80E-12 5.61E-13 3.36E-12 5.61E-13 9/20/89, Page 10.2.2.3.18 - 2
l-ANNUAL EXERCISE, Revision 1.0 L -
- j. l GAMMA SPECTRUM ANALYSIS 4 CANBERRA SPECTRAN-F V3.00 SOFTWARE -
NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT ! SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: . FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1515- ; i RADIONUCLIDES ANALYSIS REPORT ! ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 6.11E-10 1.22E-10 7.33E-10 1.46E-10. I-132 8.85E-10 1.77E-10 1.06E-09 2.12E-10! I-133 1.25E-09 2.50E-10 1.50E-09 2.99E-10i I-134 1.37E-09 2.74E-10 1.64E-09 3.27E-10 I-135 1.17E-09 2.33E-10 1.40E-09 2.79E-10 TOTAL 5.28E-09 1.06E-09 6.33E-09 1.26E-09 i 9/20/89, Page 10.2.2.3.19 l
i. I,- ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE . NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE:-2.55E+04 CC L DATE COLLECTED ON: 9/27/89 AT 1515 RADIONUCLIDES ANALYSIS REPORT J ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 7.35E-13 1.48E-13 8.83E-13 1.76E-13 Cs-137 5.70E-13 1.14E-13 6.84E-13 1.37E-13 Mn-54 1.15E-13 2.31E-14 1.38E-13 2.76E-14 Co-60 6.22E-13 1.25E-13 7.46E-13 1.49E-13 Co-58 4.83E-13 9.68E-14 5.80E-13 1.16E-13 Fe-59 5.73E-13 1.15E-13 6.87E-13 1.37E-13 TOTAL 3.10E-12 6.21E-13 3.72E-12 7.42E-13 i 9/20/89, Page 10.2.2.3.19 - 2
4 i
' ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS
' CANBERRA'SPECTRAN-F V3.00 SOFTWARE .
'NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT i
SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE. LOADED-SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1530 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION.IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 6.85E-10 1.37E-10 8.22E-10 1.64E-10l
--I-132 9.92E-10 1.99E-10 1.19E-09 2.37E-10j I-133 1.40E-09 2.81E-10 1.68E-09 3.35E-10j I-134 1.53E-09 3.08E-10 1.84E-09 3.67E-101 I-135 1.31E-09 2.62E-10 1.57E-09 3'.13E-10
- ' TOTAL 5.92E-09 1.19E-09 7.10E-09 1.42E-09 l l i
l i l i l i 9/20/89, Page 10.2.2.3.20 L___________-__-__ _ _-
! ANNUAL' EXERCISE, Revision 1.0 ic GAMMA SPECTRUM ANALYSIS CANBERRA'.SPECTRAN-F V3.00 SOFTWARE *
(. .NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT H
; SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC
' DATE COLLECTED ON:-9/27/89 AT 1530-RADIONUCLIDES ANALYSIS REPORT.
ACTIVITY' CONCENTRATION IN' uCi/cc NUbLIDE MEASURED ERROR CORRECTED' ERROR ~
.Cs-134-
~
7.84E-13 1.57E-13 '9.41E-13 1.885 .Cs-137 6.19E-13 1.24E 7.43E-13 1.48E-13 Mn-54 1.29E-13 2.58E-14 1.55E-13 3.09E-14 Co-60: 6'.97E-13 -1.39E-13 8.36E-13 1.67E-13 Co-58 :5.42E-13 1.09E-13 6.50E-13 1.30E-13
.Fe-59 6.42E-13 1.29E-13 7.71E-13 1.53E-13 TOTAL 3.41E-12 6.84E-13 4.10E-12 8.17E-13 9/20/89,'Page 10.2.2.3.20 - 2
lj.. , ANNUAL EXERCISE,' Revision 1.0' o l; I
')
GAMMA SPECTRUM ANALYSIS CANBERRA'SPECTRAN-F V3.00 SOFTWARE- J f NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT
. SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY. DESCRIPTION: FACE LOADED ,
SAMPLE SIZE: 2.55E+04 CC I DATE-COLLECTED ON: 9/27/89 AT 1545 i RADIONUCLIDES ANALYSIS REPORT
. ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 7.62E-10 1.53E-10 9.15E-10 1.82E-10:
I-132 1.10E-09 2.22E-10 1.33E-09 2.65E-10l I-133 1.56E-09 3.13E-10 1.87E-09 3.73E-10 I-134 1.71E-09 -3.42E-10 2.05E-09 4.08E-10 I-135 1.45E-09 2.92E-10 1.75E-09 3.48E-10 TOTAL 6.59E-09 1.32E-09 7.91E-09 1.58E-09 L 9/20/89, Page 10.2.2.3.21
ANNUAL EXERCISE, Revision 1.0
^~ GAMMA SPECTRUM A'NALYSIS f
CANBERRA SPECTRAN-F V3.00 SOFTWARE . NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT. SAMPLE DESCRIPTION: WRGM PARTICULATE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE' SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1545 RADIONUCLIDES ANALYSIS REPORT. ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 8.36E-13 1.68E-13 1.00E-12 -2.00E Cs-137 6.70E-13 1.34E-13 8.04E-13 1.60E-13 Mn-54 1.43E-13 2.88E-14 1.72E-13 3.43E-14 Co 7.76E-13 1.55E-13 9.31E-13 1.86E-13 Co-58 6.03E-13 1.21E-13 7.24E-13 1.45E-13 Fe-59 7.14E-13 1.43E-13 8.58E-13 1.71E-13 TOTAL 3.74E-12 7.50E-13 4.49E-12 8.96E-13 9/20/89, Page 10.2.2.3.21 - 2
ANNUAL EXERCISE, Revision 1.0 GAMMA SPECTRUM ANALYSIS CANBERRA SPECTRAN-F V3.00 SOFTWARE NEW HAMSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM IODINE GEOMETRY DESCRIPTION: FACE LOADED SAMPLE SIZE: 2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1600 RADIONUCLIDES ANALYSIS REPORT ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR I-131 8.43E-10 1.69E-10 1.01E-09 2.02E-10! I-132 1.22E-09 2.45E-10 1.47E-09 2.92E-10 I-133 1.72E-09 3.46E-10 2.07E-09 4.12E-10 I-134 1.99E-09 3.79E-10 2.27E-09 4.52E-10 I-135 1.61E-09 3.22E-10 1.93E-09 3.84E-10 . l TOTAL 7.28E-09 1.46E-09 8.74E-09 1.74E-09 9/20/89, Page 10.2.2.3.22
0 I 1 I ANNUAL EXERCISE, Revision 1.0 1 i I 1 l i _ _ . . ~ _ _ m ..
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'+ NEW HAMPSHIRE YANKEE CHEMISTRY DEPARTMENT SAMPLE DESCRIPTION: WRGM PARTICULATE :
GEOMETRY DESCRIPTION: FACE LOADED
- SAMPLE SIZE:-2.55E+04 CC DATE COLLECTED ON: 9/27/89 AT 1600 RADIONUCLIDES ANALYSIS REPORT
' ACTIVITY CONCENTRATION IN uCi/cc NUCLIDE MEASURED ERROR CORRECTED ERROR Cs-134 8.89E-13 1.78E-13 1.07E 2.13E-13 Cs-137 7.24E-13 1.45E-13 8.68E-13 1.73E-13 Mn-54 1.59E-13 3.19E-14 1.90E-13 3.80E-14 Co-60 8.58E-13 1.72E-13 1.03E-12 2.05E-13 Co-58 6.67E-13 1.34E-13 8.01E-13 1.60E-13 Fe-59 '7.90E-13 l'.58E-13 9.49E-13 1.89E-13 TOTAL 4.09E-12 8.18E-13 4.90E-12 9.78E-13 l
I 9/20/89, Page 10.2.2.3.22 - 2 {
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1 1989. GRADED EXERCISE - v, c10.3 METEOROLOGIC Al D AT A i n I
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NOTE TO CONTROLLER , Lt VE TIME METEOROLOGY WILL BE USED THROUGHOUT THE DRILL. l See Section 40 for details concernino dissemination of data 4 l
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l 8 l _ l NEW HAMPSHIRE YANKEE SEABROOK STATION 1989. GRADED EXERCISE 10.4 ONSITE OUT-OF-PL ANT DAT A h-i NOTE TO CONTROLLER ALL ON$iTE OUT-OF-PLANT READINGS ARE "AS READ" See Section 40 for detatis concernina dissemination of data.
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~s NOTE TO CONTROLLER ALL OFFSITE READINGS ARE "AS READ" .See Section 4.0 f or-details concernino dissemination of data.
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r 1 i 1 NEW HAMPSHl'tE YANKEE
, SEABROOK STATION
, 1989 GRADF.D EXERCISE 11.0 REfF_LPENCE MATERIAL
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9' j L .. j l I I 4 < NEW HAMPSHIRE YANKEE
- SEABROOK STATION' 1989 GRADED EXERCISE I 1.0 REFERENCE SECTION I l'.I General Discussion i
l The major radiological Impact begins with a 80 gallon per minute leak from a Reactor Coolant System (RCS) Res1 stance: Temperature Detector (RTD) isolation valve. The leakage from the RTD isolation valve increases to-approximately 1000 GPM, which causes an increase in the containment radioactivity . Inventory. The Intent of this scenario Is to provide operational and ' radiological data which is realistic in terms plant response, anticipated exposure rates, contamination levels, radiation monitor indications and airborne activities. The release pathway in this scenario is limited to ' design basis-containment leakage of 0.1%-from the containment free volume for the first 24 hours after the event. The amount of radioactivity released to the. environment from containment leakage is well below any detectable levels on or offsite. Consequently, there are no protective actions recommendations warranted based on radiological. conditions. The f actors cons 1dered in the release determination Include: o increasing containment source term versus time. o Containment source term reduction due to radioactive decay. o Filtration of containment leakage through available ventilation equipment. 4 4 Page 11.0-2
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NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE 1 z 11.0 REFERENCE SECTION i 11.2 Development of inolant Data 1
- The initial source term activities were calculated usino the Core Damage k Assessment Methodology, Appendix B," Selected- Fission Product '
inventories, ORIGEN.2, For a Full power Operation Cycle of Seabrook Station." The initial coolant system source activity shownterm was scaled downward to the reactor below.
- 11.2.1 Reactor Coolant Activity An initial post trip activity concentration of 2.1SE-03 uC1/ml was used as the principal source term in this scenario. This concentration was used to approximate normal reactor coolant system radioactivity concentrations for a typical Westinghouse pressurized water reactor. The Initial reactor coolant system radioactivity concentrations are shown in Table 11.2.1.
The following effects are included in the RCS source term calculations:- 11.2.1.1 Radioactive decay is included in the calculations following the plant trip. 11.2.1.2 Dilution by makeup water addition. I1.2.1.3 Steam partitioning of the particulate and fodines from the RCS water inventory discharged into the containment. i Page 11.0-3
l Rev 0 7/22/89 l NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE.
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11.0 REFERENCE SECTION 11.3 Containment Atmosohere Activity An initial containment activity concentration of 9.61E-10 was chosen to realistically represent the containment environment following extended plant operations. This concentration is roughly equivalent. to 1 MPC of unknown airborne activity. The following effects are included in the containment source term calculations: 11.3.1.I Varlable rad 10acttvtty concentration increases proportional to the reactor coolant: System leakage rate. 11.3.1.2 99% of the RCS noble gas activity is released to the containment over the course of the accident. L 11.3.2 Containment Atmosphere Activity 11.3.2.1 14% of the RCS radiolodine inventory becomes airborne. I1.3.2.2 10% of the RCS particulate inventory becomes airborne. I1.3.2.3 Radioactive decay of all radionuclides discharged into the containment. Page 11.0-4 t - - . . _ _ - - _ - - - _ - - - - - - -
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, Rev 0 7/22/89 NEW HAMPSHIRE YANKEE SEABROOK STATION 1989 GRADED EXERCISE l
11.4 INPL ANT A ADI ATION FIELCS 11.4.1 Dose Rates { Inplant dose rates were estimated using the Post Accident Radiation ) Shielding Report "9763.006-5-N-10. Inplant dose rates presented in this scenario were determined to be equivalent to the dose rates encountered during normal plant operations. l 11 A.2 Airborne Concentration Airborne radioactivity concentrations are based on routine radiological survey results. For this scenario, there are no areas which will increase in l airborne concentration other than the Containment building. Areas shown to have pre-existing airborne concentration are attributed to radon and its I daughters. 11.4.4 Smearable Contamination Smearable contamination levels presented in this scenario are based on routine radiological survey results. For this scenario, there are no areas which will become radioactively contaminated. 11.5 RADI ATION MONITOR AESPONSE I1.5.1 Area Radiation Monitors initial and drill Radiation Data itnitorino System (RDMS) Indications I were obtained from actual RDMS readouts. Certain area radiation monitor readings, for monitors in the vicinity of normal letdown system components, were scaled upward to reflect anticipated readings during full power operations and immediately following shutdown. The post LOCA monitor readings were calculated using the activity weighted fractional gamma energies of all airborne radionuclides released to the containment. For this scenarlo, there is insufficient airborne activity to cause the containment post LOCA monitors to respond. l Page 11.0-5
n i Rev 0 l 7/22/89 NEW HAMPSHIRE YANKEE 1 SEABROOK STATION
. 1989 GRADED EXERCISE .
11 S.2 Process Radiation Monitors Process radiation monitor responses were calculated based on the conversion factor 8.0e-9 uC1/ml Der com. This f actor was obtained from the Radiation Monitoring System Description. The airborne or liquid activity was calculated as described in section 11 A2. 11..S.3 Ef fluent Radiation Monttors Effluent radiation monitor responses were calculated using the activity concentrations described in sectIon 11.S.2 multiplied by a unit conversion factor and effluent flow rate. 11.6 SAMPLE DOSE RATES Dose rates from post accident samples were calculated using: Dose rate @ l ft. (rem /hr) = 6 C E N Where ' E = average gamma energy In Mev C = number of curies in the sample N = number of photons per disintegration. All survey values are rounded-of f to provide realistic survey meter responses. Where appropriate, the dose rates include contribution from various inplant systems (i.e., piping, vent ducting, etc.). These contributions also are reflected in the area radiation monitor readings. I 1.7 FIELD MONITOAING DATA Due to the limited amount of containment radioactivity leakage provided in this scenario, all field monitoring readings are "AS READ." i i Page 11.0-6 j
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' NEW HAMPSHIRE YANKEE SEABROOK STATION
, 1989 GRADED EXERCISE ,
, i. ; Table 11.2.1 INITI AL REACTOR COOLANT ACTIVITY Nuclides Concentration (UCi/cc) Kr-85m 1.17E-04 Kr-85 2.95E-06 Kr-87 2.26E-04 Kr-88 3.18E , Xe-131 m 4 45E-06 Xe-133m 2.82E-05 . Xe-133 8.99E-04 Xe-135 1.75E-04 l-131 4.41 E-05 1-132 6.39E-05 1-133 9.01 E l-134 9.87E-05 l-135 8.41 E-05 Cs-134 4.09E-08 i
~
Cs-137 2.04E-08 Mn-54 1.16E-08 Co-60 6.28E-08 l Co-58 4.88E-08 Fe-59 5.78E-08 i Total 2.15E-03
)
Dose Equivalent 1-131 7.94E-05 Noble Gases 1.70E-03 Gross lodines 3.37E-04 ) ' Particulate 2.01 E-07 i i 4 Page 11.0-7
h m. y' [. NEW HAMPSHIRE YANKEE SEABROOK STAT!0N 1989 GRADED EXERCISE 12.0 EVALUATION MATEAI AL
l l l 1 l l NEW HAMPSHIRE YANKEE SEABROOK STATION . I 1989 GRADED EXERCISE j
)
12.0 EVALUATION MATERIAL ' The evaluation material will be handed out to controllers at the controllers' brief. 1
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g .. , UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
'89 GCI 16 P3 32 ATOMIC SAFETY AND LICENSING BOARD p;
Before the Administrative Judges: 00 2 ' , ,g, Ivan W. Smith, Chairman Dr. Richard F. Cole Kenneth A. McCollom l li
)
In the Matter of ) Docket Nos. 50-443-OL j ) 50-444-OL PUBLIC SERVICE COMPANY ) (Off-Site EP) OF NEW HAMPSHIRE, EI A_L. )
)
(Seabrook Station, Units 1 and 2) ) October 13, 1989
)
CERTIFICATE OF SERVICE I, Leslie Greer, hereby certify that on October 13, 1989, I made service of the within INTERVENERS' SECOND MOTION TO ADMIT CONTENTIONS ON THE SEPTEMBER 27, 1989 EMERGENCY PLAN EXERCISE by Federal Express as indicated with (*) and by first class mail to:
*Ivan W. Smith, Chairman *Kenneth A. McCollom Atomic Safety & Licensing Board 1107 W. Knapp St.
U.S. Nuclear Regulatory Stillwater, OK 74075 Commission East West Towers Building
- Docketing and Service 4350 East West Highway U.S. Nuclear Regulatory Bethesda, MD 20814 Commission Washington, DC 20555
*Dr. Richard F. Cole Paul McEachern, Esq.
Atomic Safety & Licensing Board Shaines & McEachern U.S. Nuclear Regulatory Commission 25 Maplewood Avenue East West Towers Building P. O. Box 360 4350 East West Highway Portsmouth, NH 03801 Bethesda, MD 20814 l
l
- Robert R. Pierce, Esq.
- Thomas G. Dignan, Jr. , Esq.
Atomic Safety & Licensing Board Katherine Selleck, Esq. U.S. Nuclear Regulatory Commission Ropes & Gray East West Towers Building One International Place ; 4350 East West Highway Boston, MA 02110 Bethesda, MD 20814 H. Joseph Flynn, Esq. *Mitzi A. Young, Esq. Assistant General Counsel Edwin J. Reis, Esq. Office of General Counsel U.S. Nuclear Regulatory Federal Emergency Management Commission Agency Office of the General Counsel 500 C Street, S.W. 15th Floor Washington, DC 20472 11555 Rockville Pike Rockville, MD 20852 Atomic Safety & Licensing Robert A. Backus, Esq. Appeal Board Backus, Meyer & Solomon U.S. Nuclear Regulatory 116 Lowell Street Commiscion P.O. Box 516 Washington, DC 20555 Manchester, NH 03106 Atomic Safety & Licensing Board Jane Doughty U.S. Nuclear Regulatory Commission Seacoast Anti-Pollution League Washington, DC 20555 5 Market Street Portsmouth, NH 03801 Charles P. Graham, Esq. Barbara St. Andre, Esq. Murphy & Graham Kopelman & Paige, P.C. 33 Low Street 77 Franklin Street Newburyport, MA 01950 Boston, MA 02110 Judith H. Mizner, Esq. R. Scott Hill-Whilton, Esq. 79 State Street Lagoulis, Hill-Whilton 2nd Floor & Rotondi Newburyport, MA 01950 79 State Street Newburyport, MA 01950 Dianne Curran, Esq. Ashod N. Amirian, Esq. Harmon, Curran, & Towsley 145 South Main Street Suite 430 P.O. Box 38 2001 S Street, N.W. Bradford, MA 01835 Washington, DC 20008 Senator Gordon J. Humphrey Senator Gordon J. Humphrey U.S. Senate One Eagle Square, Suite 507 Washington, DC 20510 Concord, NH 03301 (Attn: Tom Burack) (Attn: Herb Boynton)
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. John P. Arnold,' Attorney. General .Phillip Ahrens, Esq.
Officei cf the Attorney General Assistant Attorney General 25~ Capitol Street' Department of-the Attorney
' Concord, NH'03301 General.
Augusta, ME 04333
-William S.. Lord. Board of Selectmen Town Hall - Friend Street Amesbury, MA 01913 COMMONWEALTH OF MASSACHUSETTS JAMES M. SHANNON ATTORNEY GENERAL John Traficonte Chief, Nuclear Safety Unit Leslie Greer Assistant Attorney General Nuclear Safety Unit Department of the Attorney General one Ashburton Place Boston, MA 02108-1698 (617) 727-2200 DATED: . October 13, 1989 l
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