ML20151A335

Temporary Change Notice 1-2 to Rev 1 to Operations Div Procedure SO123-0-14, Notification & Reporting of Significant Events

ML20151A335
Person / Time
Site:	San Onofre
Issue date:	06/16/1988
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20151A165	List: ML20151A162 ML20151A335 ML20151A360 ML20151A364 ML20151A388 ML20151A390 ML20151A404 ML20151A414 ML20151A417 ML20151A427 ML20151A436 ML20151A439 ML20151A651 ML20151A661 ML20151D441 ML20151D513
References
SO123--14, SO123-0-14, NUDOCS 8807190340
Download: ML20151A335 (45)

Text

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NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 1 0F 44 COMPLETE REVISION TCH /-4 EFFECTIVE DATE November 19. 1987 NOTIFICATION AND REPORTING 0F SIGNIFICANT EVENTS TABLE OF CONTENTS SECTION.

PK1 1.0 OBJECTIVES 2

2.0 REFERENCES

2 3.0 PREREQUISITE 3 4.0 PRECAUTIONS 3 5.0 CHECKLIST (S) 4 6.0 PROCEDURE 4 6.1 Responsibilities 4 6.2 Events Requiring Immediate One-Hour Telephone Notification -

5 6.3 Events Requiring Four-Hour Telephone Notification 8 6.4 Events Requiring Twenty-Four Hour Telephone Notification 10 6.5 Conditions Requiring Immediate Follow-up Telephone Notification 11 6.6 Notification Guidelines 12 6.7 NRC Telephone Notification Guidelines 12 6.8 State Office of Emergency Services (S0ES) Communication Guidelines 13 6.9 Operations Interdepartmental Notification Guidelines 14 6.10 Written Reports 14 7.0 RECORDS 17 ATTACHMENTS 1 Definitions 18 2 Effluent Reporting Requirements Guidelines 23 3 Emergency Telephone Numbers for Notification and Reporting 28 4 Operations Reporting Requirements 30 5 Communications Systems Reportability Worksheet 38 6 Nuclear Regulatory Commission Event Notification Form and Local Offsite Agency Follow-up Notification (FUN) 42 24649 .cln QA PROGRAM AFFECTING

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123 0-14 REVISION 1 PAGE 2 0F 44 TCN /-d NOTIFICATION AND REPORTING 0F SIGNIFICANT EVENTS 1.0 OBJECTIVES 1.1 To identify the conditions that require notification of the United States Nuclear Regulatory Commission (USNRC) by te N /....e and provide instructions to accomplish this notification.

1.2 To provide a comprehensive listing of events that require Operations Notifications to Station Management, offsite agencies and other SCE organizations.

2.0 REFERENCES

2.1 NRC Commitments 2.1.1 Units 1, 2 and 3 Technical Specifications 2.1.2 10 CFR 20, Appendix B, Table II 2.1.3 10 CFR 20.402, "Reports of Theft or Loss of Licensed Material" ru 2.1.4 10 CFR 20.403, "Notification of Incidents" 2.1.5 10 CFR 50.54, "Conditions of Licenses" 2.1.6 10 CFR 50.72, "Immediate Notification Requirements for Operating Nuclear Power Reactors" 2.1.7 10 CFR 50.74, "Notificatica of Change in Operator or Senior Operator Status" 2.1.8 10 CFR 55.53, "Conditions of Licenses" 2.1.9 NUREG-1022, Supplement No.1, License Event Report System 2.2 Procedures 2.2.1 S0123-VI-0.9, "Documents - Author's Guide to the Preparation of Site Orders, Procedures, and Instructions" 2.2.2 S0123-VIII-0.301, "Offsite/0nsite Communications Checks"

~

2.2.3 S01(23)-VIII-1, "Recognition and Classification of Emergencies" 2.3 0_tflee t 2.3.1 IE Information Hotice 85 78, "Event Notification" l 2.3.2 NRC Region V Letter to Dr. L. T. Papay from R. H. Engleken, l

dated September 4, 1981 l

• ' NUCLEAR CENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 TCH /4 PAGE 3 0F 44

2.0 REFERENCES

(Continued) 2.3.3 NRC Region dated V Letter April 27, 1982 to Dr. L. T. Papay from R. H. Engleken, 2.3.4 Letter from G. T. Gibson to H. E. Morgan, Au "Interpretation - Technical Specification, .' gust 31, B, ppendix 1983, Section 4.1, Unusual Fish Loss" 2.3.5 Letter, R. W. Krieger to A. E. Chaffee dated September 26, 1984, "Engineered Safety Feature Valve Failure" 2.3.6 Memo, J. G. Haynes to R. W. Krieger, dated September 26, 1984, "Standby Statements of Press Releases" 2.3.7 Letter from K. Helm to W. Marsh, dated December 22, 1983, "Radioactive Reporting Effluent Guidelines for 10 CFR 50.72 NRC Requirements" 2.3.8 Letter to J. R. Tate from M. P. Short, November 23, 1981, "Notification of Shift Technical Advisors" 2.3.9 CAR S0-P-974, "Snubber Stroke Testing Program" 2.3.10 System Operating Bulletin, No. 12 2.3.11 Telephone discussion with the NRC by G. Gibson, dated 0ctober 9,1987, "Preplanned Engineered Safety Features (ESF) Actuations" 3.0 PRERE0VISITE 3.1 Prior to use of user controlled copy of this Site Document to perform work, verify it is current by checking a controlled copy and any TCNs; or by use of the method described in S0123-VI-0.9.

4.0 PRECAUTIONS 4.1 The reportability requirements of this procedure should be reviewed fully when an assessment is being made, as there may be more than one reportability requirement under which a notification or report must be made.

! 4.2

! Any notification using the Emergency Notification System requires a followup written report by the Compliance Duty Representative (COR The completed copy of Attachment 6 shall be used for this purpose.).

4.3 Periodically, the CDR will report to the Shift Superintendent concerning notifications to NRC made by Compliance. In such cases, ensure an adequate log is maintained as this is one of the principal means of informing Operations Division personnel of the event.

4.4 The Shift Superintendent should be aware that he typically is first to know of possible reportable conditions; therefore, he must review this procedure and notify others who may have to make reports (e.g. COR).

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 4 0F 44 TCN M 4.0 PRECAUTIONS (Continued) 4.5 Any 3.0.3 entry or exceeding an LCO requires a written report and all steps in Sections 6.2 and 6.3 should be reviewed to ensure that no other reporting conditions apply.

5.0 CHECKLIST (S1 5.1 None 6.0 PROCEDURE NOTE: The capitalized words or phrases in the steps of this procedure are defined in Attachment 1.

6.1 Resoonsibilities 6.1.1 If a significant event occurs, it is_ the responsibility of the Shift Superintendent or CDR to ensure that the NRC is notified and that the notification is documented.

.1 The Shift Superintendent shall log all NRC telephone NOTIFICATIONS regardless of who made the call.

6.1.2 Within the time available, the Shift Superintendent should confer with the on-shift Shift Technical Advisor (STA) at any time, and with Station management during normal working hours when a significant event occurs; however, Station management concurrence is not reouired prior to this notification.

NOTE: Notification responsibility is delineated in bold print for each event listed in steps 6.2, 6.3 and 6.4 (e.g. OPS, CDR).

6.1.3 Sections 6.2, 6.3 and 6.4 list NRC notification i

requirements and assign primary responsibility for making i

the notification.

.1 Upon identification of an event listed in Section 6.2, 6.3,

or 6.4, follow Sections 6.6 and 6.7 to make the l notification.

6.1.4 When the CDR is responsible to make the notification and it is evident that the CDR cannot be contacted to make the required NRC notification within the specified time, then the Shift Superintendent shall make the notification.

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. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 IS 1 PAGE 5 0F 44 6.0 PROCE0VRE (Continued) ,

6.1.5 The Shift Superintendent is in the unique position of being one of the first in the management chain to become aware of unusual, although non-NRC reportable occurrences. For events in this category, which could trigger media,or public concern, it is the Shift Superintendent's responsibility to ensure that the Operations Manager, or designee, is promptly informed so a decision can be made as to whether a follow-up briefing of senior management is required.

6.2 Events Reauirino Immediate One-Hour Telephone Notification 6.2.1 The declaration of any of the emergency classes OPS specified in Emergency Plan Implementing Procedure (EPIP)

S01(23)-VIII-1, "Recognition and Classification of Emergencies." (10 CFR 50.72, a.1.1)

.1 In this situation, make the appropriate supervisory notifications per Attachment 4, terminate the use of this procedure and proceed with the EPIPs.

[1] 6.2.2 Th5 INITIATION OF ANY NUCLEAR PLANT SHVTDOWN required OPS by the plant's Technical Specifications. (10 CFR 50.72, b.1.i.A)

.1 If' the shutdown is performed early, as a result of a condition in which the LC0 Action Statement would have required a shutdown, the shutdown is still reportable.

6.2.3 Any deviation from the nlant's Technical Specifications OPS authorized by 10 CFR 50.54(x) as follows: (10 CFR 50.72, b.1.i.8)

.1 A licensee may take reasonable action that departs from a license condition or a Technical Specification (contained in a license issued under this part) in an emergency when this action is immediately needed to protect the public '

health and safety and no action consistent with license conditions and technical specifications that can provide adeouate or equivalent protection is immediately apparent.

6.2.4 Any event or condition DURING OPERATION that results in the OPS condition of the NUCLEAR POWER PLANT,' including its PRINCIPAL SAFETY BARRIERS, being SERIOUSLY DEGRADED or results in the nuclear power plant being: (10 CFR 50.72, b.l.ii)

.. In an UNANALYZED CONDITION that significantly compromises CDR plant safety; (10 CFR 50.72, b.l.ii.A)

[1] Review Emergency Plan for possible Emergency Event classification.

. NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 6 0F 44 TCN /-JL 6.0 PROCEDURE (Continued) ,

6.2.4.2 In a condition that is outside the DES!GN BASIS of the CDR plant; or (10 CFR 50.72, b.1.ii.8)

.3 In a CONDITION NOT COVERED BY THE PLANT'S OPEhATING AND OPS EMERGENCY PROCEDURES. (10 CFR 50.72, b.1.ii.C)

[1] 6.2.5 Any event or condition that results in an unisolable leak OPS in the Reactor Coolant System exceeding 7 gpm for Unit I or 11 gpm for Units 2/3. (This is considered reportable under 10 CFR 50.72, b.1.ii)

[1] 6.2.6 Any NATURAL 7 HEN 0MENON OR OTHER EXTERNAL CONDITION that OPS poses an actual threat to the safety of the NUCLEAR DOWER PLANT or SIGNIFICANTLY HAMPERS SITE PERSONNEL IN THE PERFORMANCE OF DUTIES NECESSARY FOR THE SAFE OPERATION OF THE PLANT. (10 CFR 50.72, b.1.iii)

[1] 6.2.7 Any event that results or should have resulted in OPS Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a y_alid signal.

(10 CFR 50.72, b.1.iv) 6.2.8 Any event that results in a MAJOR LOSS OF:

(10CFR50.72,b.1.v)

[1] .1 Emergency assessment capability (e.g., Significant portion OPS of Control Room indication),

.1.1 In this case, a judgement will be necessary and management input should be obtained prior to making the NOTIFICATION, time permitting.

OPS .2 Offsite response capability (e.g., EMERGENCY NOTIFICATION SYSTEM),or i

NOTES: 1. Guidelines for Communications Systems Reporting Requirements are provided in Attachment 5.

2. May be discovered during communication checks per S0123-VIII-0.301.

CDR .3 Communications capability (e.g., Offsite Notification System).

[1] Review Emergency Plan for possible Emergency Event classification.

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 7 0F 44 TCN / e2-6.0 PROCEDURE (Continued)

(1) 6.2.9 Any event that poses an actual threat to the safety of OPS the NUCLEAR POWER PLANT or SIGNIFICANTLY HAMPERS SITE PERSONNEL,-(including Tech. Spec. required fire watch personnel), IN THE PERFORMANCE OF OUTIES NECESSARY FOR THE SAFE OPERATION OF THE NUCLEAR POWER PLANT, including fires, toxic gas releases, or radioactive releases.

(10 CFR 50.72,b.l.vi)

[1] 6.2.10 Violation of a Technical Specification Safety limit OPS (Ref. Technical Specifications, Section 6.7).

.1 If the Unit was operating, this event is also re cortable per Step 6.2.2.

[1] 6.2.11 Any event requiring the transport of a radioactively-OPS contaminated person to an offsite medical facility for treatment. (This is considered an Unusual Event per S01(23)-VIII-1)

(1) 6.2.12 , Any of the following 10 CFR 20.403(a) events w'here any CDR incident involving by-products, source or special nuclear material may nave caused or threatens to cause:

.1 Exposure of the whole body of an individual to 25 REM or more of radiation; exposure of the skin of the whole body of an individual to 150 REM or more of radiation; exposure of the feet, ankles, hands or forearms of any individual to 375 REM or more of radiation;

.2 The release of radioactive material in concentrations which, if averaged over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5,000 times the limits specified for such materials in 10 CFR 20, Appendix B. Table II.

.3 A loss of one working week or more of facility operation; or

.4 Damage to property in ex. cess of $200,000.

6.2.13 A loss or theft of LICENSED MATERIAL has occurred in such CDR quantities that it appears to the licensee that a p.f j

substantial hazard may result to persons in unrestricted areas. (10 CFR 20.402(a)(1))

(1) Review Emergency Plan for possible Emergency Event classification.

. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 8 0F 44 TCN /_-dL 6.0 PROCEDURE (Continued) 6.3 Events Reauirina Four-Hour Telechone Notification 6.3.1 Any event, found while the reactor is shutdown, that, CDR had it been found while the reactor was in operation, would have resulted in the NUCLEAR POWER PLANT, including its PRINCIPAL SAFETY BARRIERS, being seriously degraded or being in an UNANALYZED CONDITION that SIGNIFICANTLY COMPROMISES PLANT SAFETY. (10 CFR 50.72, b.2.i.)

6.3.2 Any event or condition that results in manual or automatic OPS actuation of any ENGINEERED SAFETY FEATURE (ESF), including the REACTOR PROTECTIVE SYSTEM (RPS). This includes systems not required to be operable for the present mode per the Technical Specifications. See exceptions below.

(10 CFR 50.72, b.2.ii)

NOTE: All actuations need to be carefully evaluated to ensure correct and complete Safety System operation occurred once the signal was present.

(Whether or not the actuation was anticipated.)

.1 H an ESF system is not required to be operable and has been physically and administratively removed from service such that it cannot perform its intended function (e.g.,

manual discharge valves are shut, breakers are open), then a spurious actuation of part of the system (e.g., the pump starts but the discharge valve remains shut) is not reportable. (NUREG 1022, Supplement 1, Q & A 6.9) or

.2 H an ESF actuation results from, and is part of, a PREPLANNED SEQUENCE using an Operations procedure, and the procedure controlling the activity specifically identifies an ESF actuation is intended to occur, then the ESF actuation need not be reported. (Reference 2.3.11) or

.3 H all of the following criteria are met, then an ESF l actuation need nql be reported (Reference 2.3.11):

.3.1 The actuation results from a preplanned evolution (not l performed by Operations) related to the ESF; and

.3.2 The cognizant Control Operator is notified immediately prior to the activity which could cause th actuation; and

.3.3 The notification of the potential actuation is documented in the Control Operator's Log.

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1 NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE E0123-0-14 REVISION 1 PA;:E 9 0F 44 TCH / -jl, 6.0 PROCEDURE (Continued) 6.3.3 Any event or condition that alone could have prevented the CDR fulfillment of the safety function of structures or systems that are needed to:

NOTE:

Refers to loss of more than one train on multiple train systems.

.1 Shut down the reactor and maintain it in a safe shutdown condition, (10 CFR 50.72, b.2.iii.A);

.2 Remove residual heat (10 CFR 50.72, b.2.iii.B);

.3 Control the release of radioactive material (10 CFR 50.72, b.2.iii.C); or

.4 Mitigate the consequences of an accident (10 CFR 50.72, b.2.iii.0).

NOTE: Guidelines for Effluent Rcporting Requirements are provided in Attachment 2.

(1) 6.3.4 Any airborne radioactive release that exceeds 2 times CDR the applicable concentrations of the limits specified in Appendix 8, Table II, of 10 CFR 20 in unrestricted areas, when averaged over a time period of one hour.

(10 CFR 50.72, b.2.iv.A)

[1] 6.3.5 Any liquid effluent release that exceeds 2 times the CDR limiting combined Maximum Permissible Concentration (MPC) (see Note 1 of Appendix 8 to 10 CFR 20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. (10 CFR 50.72, b.2.iv.B)

.1 NOTIFICATIONS made under this paragraph also satisfy the requirements of 10 CFR 20.403, paragraphs -(a.2) and (b.2).

6.3.6 Any event or situation, related to the health and safety CDR of the public or onsite personnel, or protection of the environment, for which a news release is planned or NOTIFICATION to other government agencies has been or will be made. (10 CFR 50.72, b.2.vi)

.1 Such an event may include an onsite fatality or inadvertent release of radioactive contaminated caterials.

[1] Review Emergency Plan for possible Emergency Event classification.

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 10 0F 44 TCH /W/

6.0 PROCEDURE (Continued) l 6.4 Events Reauirina Twenty-four Hour Telechone Notification

[1] 6.4.1 Any of the following 10 CFR 20.403(b) events involving CDR licensed material that could have caused, or threaten to cause:

.1 Exposure of the whole body of any individual to 5 REM or more of radiation; exposure of the skin of the whole body of an individual to 30 REM or more of radiation; or exposure of the feet, ankles, hands or forearms to 75 REM or more of radiation;

.2 The release of radioactive material in concentrations which, if averaged over a period of twenty-four (24) hours, would exceed 500 times the limits specified for such materials in 10 CFR 20, Appendix B, Table II;

.3 A loss of one day or more of facility operatien;

.4 Damage to property in excess of $2,000.

6.4.2 Any occurrence of an unusual or important event that CDR indicates or could result in significant environmental impact (Unit 1 Technical Specification 6.16.2.b; Units 2 and 3, Appendix B, Environmental Protection Plan 4.1)..

6.4.3 Unit I specific twenty-four hour NOTIFICATIONS CDR

.1 With no Fire Suppression Water System operable ... submit a special report ... by telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ... (Unit 1 Technical Specification 3.14).

.2 Verbal report to the Resident Inspectors, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, of any failure during test or operation of a Safety Injection System Hydraulic Valve.

6.4.4 Unit 2/3 specific twenty-four hour NOTIFICATIONS CDR

[1] .1 An unusual fish loss of 4500 lbs. or more during heat treating of the Circulating Water System (Reference 2.3.4).

.2 Any applicable conditions requiring NOTIFICATION per Section 2.G. of the Facility Operating License.

[1] Review Emergency Plan for possible Emergency Event classification.

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 11 0F 44 TCH / o2-6.0 PROCEDURE (Continued) 6.5 Conditions Reouirino Immediate Follow-up Telephone Notification 6.5.1 With respect to the telephone NOTIFICATIONS made as required in Sections 6.2 and 6.3, the licensee, during the course of the event, shall immediately report the following conditions: (10 CFR 50.72, c)

NOTE: Follow-up notification should normally be made by the individual or department responsible for the initial notification. Additional information requested by the NRC on the Red Phone for a CDR notification should be referred to the CDR.

.1 Any further degradation in the level of safety of the plant, or other worsening plant conditions (including those that require the declaration of any of the Emergency Classes, if such a declaration has not been previously made);

.2 The results of ensuing evaluations or assessments of plant conditions;

.3 The effectiveness of response or protective measures taken; or

.4 Information related to plant behavior that is not understood.

6.5.2 Upon request by the NRC, the licensee shall maintain an open, continuous communication channel with the NRC Operations Center.

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, NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 12 0F 44 TCH M 6.0 PROCEDURE (Continued) 6.6 Notificati1n Guidelines 6.6.1 Prior to reporting event notification information to the NRC Operations Center required by Operations in Sections 6.2 and 6.3, the Shift Technical Advisor, Operations Duty Division Manager, Compliance Duty Representative and, if possible, the resident NRC inspector should be notified using Attachment 3.

NOTE: If questions regarding reportability can not be resolved by che Shift Superintendent, the CDR is to be contacted for consultation.

.1 If unable to contact all of the individuals in the normal reporting chain above within the specified time following the event, then make the notification to the NRC Operations Center per Section 6.7.

.1.1 In this situation, information calls should be made to the individuals identified in step 6.6.1 as soon as possible.

6.6.2 The Shift Superintendent shall notify the CDR of events which require reporting by the CDR.

.1 Additional notifications by the Shift Superintendent under these conditions is not necessary unless the CDR is unable to make the notification within the specified time limit.

6.7 NRC Telechone Notification Guidelines NOTES: 1) Duty officers manning the NRC Operations Center utilize the Event Notification Form provided in Attachment 6 for those events reported in Sections 6.2 and 6.3, (Reference 2.3.1).

Having this type of information available at the time of notification will serve to expedite the notification and evaluation process and make communications more efficient.

If circumstances cause Attachment 6 to be completed after the time of the notification ensure all information supplied to the NRC is reflected on Attachment 6.

I

2) In accordance with 10 CFR 50.72, the NRC Operations Center shall be notified as soon as possible and, in all cases, within one hour or four hours (as applicable) by telephone of the occurrence of any event listed in Sections 6.2 and 6.3.

. j

^

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 I REVISION 1 PAGE 13 0F 44 TCH /4 i

6.0 PROCEDVRE (Continued) 6.7.1 Telephone notification to the NRC Operations Center will be made via the Emergency Notification System (Red) Telephone.

The telephone is activated by lifting the receiver from the cradle. l NOTE: Red Telephone inoperability is reportable oer step 6.2.8.3.2.

.1 If the Red Telephone is inoperative, notification should be made via the alternate methods listed in Attachment 3. The alternate methods of notification listed in the attachment should be attempted in the order given. (References 2.3.2 and 2.3.3)

NOTE: After NRC notification, the completed Attachment 6 should be forwarded to the Shift Communicator for Local Offsite Follow-up Notification (FUN),

if necessary.

.6.7.2 Telephone notification to the NRC Resident Inspector (s) should be accomplished as indicated in Attachment 3 whenever initial notification red phone reports are made.

6.7.3 When event is terminated, forward the completed Attachment 6 per step 7.2.

6.8 State Office of Emeraency Services (SOES) Communication Guidelines 6.8.1 When the Plant Vent Stack Radiation Alarm or Safety Injection Actuation Alarm annunciate at the SOES, they may inquire by telephone. The SOES has been requested to call the Shift Superintendent if they have questions. If the SOES calls or the Shift Superintendent suspects that they will call, (after receipt of a SIAS or Plant Vent Stack alarm), then the following steps should be taken:

.1 If possible, prior to receipt of the call from the SOES, fill out applicable portions of Attachment 6.

.l.1 Request the Effluent Engineer / Chemistry / Health Physics gather the information for the applicable sections of Attachment 6.

.2 If the SOES calls prior to completion of Attachment 6, record the information given to the SOES on Attachment 6.

Agree to the follow up if the SOES so requests.

. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 l UNITS 1, 2 AND 3 REVISION 1 PAGE 14 0F 44 l TCH /-dL- ,

6.0 PROCEDURE (Continued) ,

1 6.8.1.3 If a follow-up notification is to be made notify the CDR who will provide the follow-up call. The CDR may require the portions of Attachment 6 used to record information given to the SOES on their initial call.

.4 SOES inquiries by telephone could constitute a 4-hour reportable event (from the telephone contact time) pursuant to 10 CFR 50.72(b)(2)(vi). Determination .of reportability should be made as follows:

.4.1 If the alarm was a result of a valid signal regardless of setpoint, the discussion between SOES and SCE is reportable.

.4.2 If the alarm was spurious or the result of a planned test of the alarm / monitor system, the discussion between SOES and SCE is nat reportable.

6.9 Ooerations Interdepartmental Notification Guidelines 6.9.1 Attachment 4 shall be used as a reference for Operations notification requirements to Station Management and other organizations.

6.10 Written Reco'rts NOTE: The Shift Superintendent has no responsibility to make written reports; however, he is in a unique position with respect to oversee the operation of the plant. This list of reports is provided so that the Shift Superintendent can consider events that require reports.

6.10.1 If the Shift Superintendent is made aware that an event listed below has occurred and/or has reason to believe a required report has not been prepared, he shall bring this to the attention of the CDR by filling out Attachment 6 as appropriate and routing it to the Plant Superintendent.

6.10.2 The events below require thirty-day written reports from Units 1, 2, or 3:

.1 Any event requiring notification per steps 6.2.3, 6.2.4, 6.2.5,6.2.8,6.2.13,6.3.2,6.3.3,6.3.4,6.3.5,or6.4.2.l,ru

,_-i.. --

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 15 0F 44 TCN S 6.0 PROCEDURE (Continued) 6.10.2.2 The completion of any nuclear plant shutdown required by the Plant's Technical Specifications.

NOTES: 1. See Attachment 4, step 1.1 for approval of voluntary 3.0.3 entries.

2. See Precaution 4.5.

.3 Any operation or condition prohibited by the Technical Specifications, or any event in which a Technical Specification LC0 and its Action Statement is not met, or a.ny condition that results in an entry into Technical Specification 3.0.3.

.4 Any event where a single cause or condition resulted in at least one independent train or channel becoming inoperable in multiple systems; or two independent trains or channels to becoming inoperable in a single system designed to:

.4.1 Shutdown the reactor and maintain it in a safe shutdown condition;

.4.2 Remove residual heat;

.4.3 Control the release of radioactive material; or

.4.4 Mitigate the consequences of an accident.

.5 Any of the following pertaining to licensed operators (Reference 10 CFR 50.74 (a), (b) and (c) and 55.53 (g)):

.5.1 Permanent reassignment from the Operations Division;

.5.2 Termination or resignation;

.5.3 Disability or illness which could affect license status or performance (coordination with Medical Department is required);

.5.4 Conviction of a felony.

1 l 6.10.3 Unit 1 - The events below require written reports:

NOTE: Time requirements for each report are listed with each step.

.1 Fire Suppression Water System (Tech. Spec. 3.14);

.l.1 Some part of the required Fir? Suppression Water System inoperable for greater than seven days (30 days).

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 16 0F 44 TCN M 6.0 PROCEDURE (Continued) 6.10.3.1.2 No Fire Suppression Water System operable (14 days).

.2 Some part of the required Spray and/or Sprinkler Syste.n inoperable for greater than fourteen days per Tech.

Spec. 3.14 (30 days);

.3 Some part of the required Fire Detection Instrumentation inoperable for greater than fourteen days per Tech.

Spec 3.14 (30 days);

.4 Limits on dose, dose commitment, and treatment of effluents are exceeded per Tech Specs. 3.15.2, 3.15.3, 3.16.2, 3.16.3, 3.16.4 or 3.17 (30 days);

.5 Limits on Environmental Monitc*ing are exceeded per Tech Specs. 3.18.1 or 3.18.2 (30 days);

.6 One or more of Radiation Monitoring Channels R-1254, R-1255, R-1256 A&B, R-1257, or R-1258 A&B is inoperable in Mades 1-4 per Tech Spec 3.5.10 (14 days).

.7 Use of either the PORVs or the RCS vent (s) to mitigate a potential RCS pressure transient per Tech Spec 3.20 .Tul (30 days).

6.10.4 Units 2/3 - The events below require written reports:

NOTE: Time requirements for each report are listed with each step.

.1 Fire Protectioc Spray and/or Sprinkler System inoperability per Tech. Spec. 3.7.8.2 (7 days);

.2 . Seismic, Meteorological or Loose Parts Monitoring Instrumentation inoperability per Tech. Specs. 3.3.3.3, 3.3.3.4 or 3.3.3.10 (10 days);

.3 Safety Limit Violations or Radiation Monitor Instrumentation inoperability per Tech. Spec. 6.7.lc or

! 3.3.3.1 (14 days);

.4 Steam Generator Structural Integrity Criteria not met per Tech. Spec. 3.4.4 (15 days);

.5 RCS Specific Activity requirements exceeded per Tech.

Spec. 3.4.7 (30 days);

.6 RCS overpressurization mitigated by the Shutdown Cooling Relief or an RCS Vent per Tech. Specs. 3.4.8.3.1 or 3.4.8.3.2 (30 days);

l . _ .

NUCLEAR' GENERATION SITE OPERATIONS UIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 17 0F 44 TCN M 6.0 PROCEDURE (Continued) 6.10.4.7 Liquid Effluent, Gaseous Effluent or Radwaste Treatment Systems actions per Tech. Specs. 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2,3, 3.11.2.4, 3.11.3, or 3.11.4 (30 days);

.8 Environmental Monitoring criteria not met per Tech.

Specs. 3.12.1 or 3.12.2 (30 days);

.9 Emergency Core Cooling System injection per Tech. Specs.

3.5.2 or 3.5.3 (90 days).

7.0 RECORDS 7.1 Telephone notification to the NRC shall be documented in the Shift Superintendent's Log Book.

7.2 Tne completed Attachment 6 shall ba copied and forwarded to Compliance as soon as possible. The original shall be forwarded to the Ple.nt Superintendent for review. Following this review, the Plant Superintendent sha.il forward the original to CDM.

I 85oos:2404g.cln

/

m

, hUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVIS10N 1 PAGE 18 0F 44 ATTACHMENT 1 TCN / y9, DEFINITIONS NOTE:

The snurce of these definitions is indicated in brackets following the definition. These definitions are intended for guidance only and must be applied with "good engineering judgment".

1.

CONDITI0rf NOT COVERED BY THE PLANT'S OPERATING AND EMERG.ENCY

~

PROCEDUPES - Any abnormal condition of the plant, evidenced by installed indication of plant parameters, but not recognized or defined as a symptor.

of an abnormal condition in any plant operating or emergency procedure.

[ Source: Compliance]

2. DESIGN BASEE - The DESIGN BASES of the plant are defined throughout the FSAR in those sections entitled "DESIGN BASIS" or "DESIGN BASES". [ Source:

Compliance]

3. DURING OPERATION - MODES 1 and 2 as defined by Technical Specifications.

[ Source: Compliance]

4. EMERGENCY NOTIFICATION S1SIEM - The red phone, or if the red phone is not

. operating, then alternate telephone systems as delineated'in Attachment 3.

[ Source: Compliance]

5. ENGINEERED SA/ETY FEATyRE These features are defined as:

a. For Unit 1 (1.) Safety Injection System (2.) Containment Isolation System (3.) Recirculation Systens (4.) Containment Spray System (5.) Diesel Generators (6.) Auxiliary Feedwater System (7.) Centrol Room Emergency Air Treatment System

[ Source: Compliance]

5. b. For Units 2 and 3 See Technical Specifications, Section 3.3.2.

ATTACHMENT 1 PAGE 1 0F 5

, NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0l?3-0-14 l REVISION 1 PAGE 19 0F 44 l ATTACHMENT-1 TCN /-L DEFINITIONS (Continued)

6. INITIAT. ION OF ANY NUCLEAR PLANT SHUT 00WN - That point in time when, while in  :

MODES 1 or 2, reactivity manipulations are commenced to place the unit in MODES 3, 4 or 5. [ Source: Compliance]

7. LICENSED MATERIAL - Source material, special nuclear material, or by-product material received, possessed, used, or transferred under a general or T"'

specific license issued by the NRC. [ Source: 10 CFR 20.3)

8. E10R LOSS OF EMERGENCY ASSESSMENT CAPABILITY. OFFSITE RESPONSE CAPABILITY OR COMMUNICATIONS CAPABILITY - Examples of events that this criterion is intended to cover are those in which any of the following are not available:

a. Safety Parameter Display System (SPDS).

b. Emergency Response Facilities (ERFs),

c. Emergency communications facilities and equipment including the Emergency Notification system (ENS).

d. Public prompt Notification System including sirens.

e. Plant monitors necessary for accident assusment.

[ Source: Federal Register pg 39043, Vol 48, No. 168, Monday, August 29, 1983)

9. NATURAL PHENOMENON OR OTHER EXTERNAL CONDITION - Acts of nature (e.g.,

tornadoes, earthquaker, floods, etc.) and external hazards (e.g., railroad tank car explosion) where the threat or damage challenges the ability of the l

plant to continue to operate in a safe manner (including the orderly shutdown and maintenance of shutdown conditions). [ Source: Federal Register, pg. 39041. ' Vol . 48, No.168, Monday, A!! gust 29,1983]

l 10. NOTIFICATU)H - Legally required transmission within specified time limits of event-rel'ted information of offsite agencies, such as the NRC, Corporate l Headquarters, St&te or Local government. [ Source: Compliance)

11. MLGLEAR POWER PLANT - Nuclear Steam Supply System (NSSS), including the Reactor Coolant System and all of those systems or components necessary for l transfer of heat from the reactor core to the ultimate heat sink. [ Source:

Compliance]

12. PREFLANNED SE0VENCE - Those operations of the NSSS and its auxiliaries that are performed in accordance with a written and properly approved procedure.

(Source: Compliance) i ATTACHMENT I PAGE 2 0F 5

--w. , , - -

. l l

i

. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCE0VRE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 20 0F 44 ATTACHMENT 1 ,

TCN /-db l DEFINITIONS (Continued)

13. PRINCIPAL SAFETY BARRIERS -

a. Fuel Cladding

b. Reactor Coolant System Pressure Boundary

c. Containment (Source: Compliance}

14. REACTOR PROTECTION SYSTEM - these Systems are defined as:

a. For Unit 1 (1.) Manual Reactor Trip (2.) Power Range, High Flux level Trip (3.) Intermediate Range, Startup Rate Trip (4.) Pressurizer, Variable Low Pressure Trip (5.) Pressurizer, High Pressure Trip (6.) Pressurizer, High Level Trip (7.) Reactor Coolant Flow -

(a) Single Loop loss of Flow Trip (Above 50% Full Power)

(b) Two Loop Loss of Flow Trip (Below 507. Full Power)

(8.) Steam /Feedwater Flow Mismatch Trip (9.) Turbine Trip (Source: Complian'ce]

b. For Units 2 and 3, see Technical Specifications, Section 3.3.1.

15. SERIOUSLY DEGRADED -

a. Fuel cladding failures in the reactor, that are widespread, or caused by unexpected factors, and would involve a release of significant quantities of fission products,

b. Cracks and breaks m the piping or reactor vessel or major components in the primary coolant circuit that have safety relevance (steam generators, reactor c olant pumps valves, etc.).

c. Unisolable leak in u e Reactor Cuolant System exceeding 7 gpm for Unit 1 or 11 gpm for Units 2/3.

d. Significant welding or material defects in the primary coolant system.

(Do not n:eet acceptance criteria of ASME Boiler and Pressure Vessel Code.)

ATTACHENT 1 PAGE 3 0F 5

1 l

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE $0123-0-14 "P71SION 1 PAGE 21 0F 44 ATTACHMENT 1 TCN / bl-DEFINITIONS (Continued)

15. SERIOUSLY DEGRADED - (Continued)

e. Serious temperature or pressure transients (exceeding those permitted by Technical Specification Heat-up and Cooldown curves).

f.

Loss of relief and/or safety valve functions during operation.

g. Loss of containment function or integrity including:

1. Containment (integrated) leakage rates exceeding the authorized limits; 2.

Loss of containment isolation valve function (as defined in Technical Specifications) during tests or operation;

3. Loss of main steam isolation valve function during test or operation, or;

4. Loss of containment cooling capability. -

h. The inability to transfer heat from the reactor cora tq the ultimate heat sink (saltwater cooling system); or otherwise, remove the heat resulting from the decay of fission products in the core after a successful reactor trip. [ Source: Federal Register, page 39042, Vol. 48, No. 168, Monday, August 29,1983]

16.

SIGNIFICANTLY COMPROMISE PLANT SAFETY - Prevent or impair engineered safety features, including the reactor protective system, from performing their intended function. (Source: Compliance]

17. EIGNIFICANTLY HAMPERS SITE PERSONNEL IN THE PERFORMANCE OF DUTIES NE FOR THE SAFE OPERATION OF THE PLANT - Prevents or inhibits operators, or other responsible personnel, from taking the action necessary to prevent or mitigate the consequences of any abnormal occurrence, or from performing a Tech. Spec. required activity. (Source: Complian a)

ATTACHMENT 1 PAGE 4 0F 5

' ,- NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 22 0F 44 ATTACHMENT 1 TCH j d DEFINITIONS (Continued)

18. UNANALYZED CONDITION - Any event or condition not within the design or licensing basis as currently docketed and approved by the NRC (source:

NUREG-1022, Supplement No. 1)

NOTE: We may use engineering judgment and experience to determine whether an unanalyzed condition existed. It is not intended that this apply to minor variations in individual parameters, or to problems concerning si.ngle pieces of equipment. For example, at any time, one or more safety-related components may be.out of service due to testing, maintenance or a fault that has not yet been repaired. Any trivial single failure or minor error in performing surveillance tests could produce a situation in which two or more often unrelated, safety-grade components are out-of-service. Technically, this is an unanalyzed condition.

Hewever, these events should be reported only if they involve functionally-related components or if they significantly compromise plant safety. When applying engineering judgment, and there is a doubt regarding whether to report or not, the NRC policy is that we should make the report. (Source: Federal Register pg. 39042, Vol. 48, No. 168, Monday, August 29,1983]

ATTACHMENT 1 24649 .cin PAGE 5 0F 5

NUCLEAR' GENERATION SITE UNITS 1,.2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 23 0F 44 ATTACHMENT 2 TCN /-sL EFFLUENT REPORTING RE0VIREMENTS GUIDELINES Effluent Guidelines for 10 CFR 50.72 NRC Reoortability (Ref. 2.3.7)

1. A planned and monitored effluent release to the unrestricted area outside the site boundary is covered under the ODCM and is not 10 CFR 50.72 NRC reportable.

II. A planned and unmonitored effluent release to the unrestricted area outside the site boundary is covered under the ODCM and effluent monitoring procedures and is not 10 CFR 50.~72 NRC reportable.

III. An unplanned and unmonitored effluent release to the unrestricted area outside the site boundary may require Event Classification per the EPIPs and is reportable as an LER.

IV. An unplanned but monitored effluent release to the unrestricted area outside the site boundary must be evaluated for reportability:

A. Guidelines: Liauid Effluent Monitors Liquid effluent is nonvolatile, consequently, it is extremely unlikely that an accidental, unplanned or uncontrolled liquid radioactive release can escape to the unrestricted area (outfall)'via a monitored flowpath. In addition, all the monitored liquid flowpaths to the outfall have both alarm isolation capabilities to terminate any inadvertent releases which may have resulted in exceeding an MPC at the unrestricted area.

Therefore, an unplanned but moni. ' red liquid effluent release to the unrestricted area is 10 CFR 50.72, b.2.IV.B NRC reportable if it has potentially violated 2 MPCs averaged over one hour. If the release has violated the 1 MPC Tech. Spec. limit, it may be declared an Unusual Event per the EPIPs, and is reportable as an LER.

l ATTACHMENT 2 PAGE 1 0F 5

m - -

I S.

NhCLEARGENERATIONSITE UN?TS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 24 0F 44 ATTACHMENT 2 TCN M IV. A. (Continued)

In particular, effluent monitors of interest are: '

UNIT 1 NOTE:

Monitor readings assume 2 cire, pumps providing dilution (300,000 gpm). Reading should be reduced as a ratio of available dilution; i.e.,

$ ,* x 1.2E5 cpm 6.0E4 cpm' (1) 1. R1216 S/G Blowdown 1.2E5 cpm - 1 MPC (1) 2. R1218 Liquid Radwaste 3.3E6 cpm - 1 MPC (2) 3. R2100 Reheater Pit Sump 8.5E4 cpm - 1 MPC (2) 4. R2101 Yard Sump 3.0E4 cpm ,1 MPC (1) Based on typical RCS isotopic mixture.

(2) Based on 1-131 (most conservative)

UNIT 2 and 3 NOTE:

Monitor readings assume 3 cire, pumps providing dilution (555,000 gpm). Reading should be altered as a ratio of available dilution; i.e.,

x 2.5E5 cpm - 3.3E5 cpm'

l. RT-7813 Liquid Radwaste Overboard Discharge 2.5E5 cpm - 1 MPC

2. RT-7821 Turbine Building Sumps 3.5E5 cpm = 1 MPC (1) 3. RT-7817 S/G BPS Neutralization Sumps 2.9E5 cpm - 1 MPC (1) 4. RT-6759 S/G E-088 Blowdown Effluent Line 1.3E5 cpm - 1 MPC (1) 5. RT-6753 S/G E 009 Blowdown Effluent Line 1.3E5 cpm = 1 MPC (1) Based on typical RCS isotopic mixture.

ATTACHMENT 2 .

PAGE 2 0F 5

~ NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 25 0F 44 ATTACHMENT 2 TCN M IV. (Continued)

8. Guidelines: Gaseous Effluent Monitors Gaseous effluent is volatile, consequently, it is more likely that an accidental, unplanned or uncontrolled gaseous radioactive release can escape to the unrestricted area via a monitored flowpath. In addition, many gaseous effluent monitors do not hwe isolation capability to terminate an inadvertent release which may have resulted in exceeding an MPC at the unrestricted area.

Using the logic contained in the ODCM and stated exprersly in the NUREG 0133, only the noble gas channel of a gaseous effluent monitor needs to be considered. The efflueni. monitor reading thresholds for 10 CFR 50.72, b.2.IV.A NRC reporting requirements are summarized in Table

1. These monitor readings correspond 2.0, l'.0 and .5 MPCs to the unrestricted area.

The 0.5 MPC and 1.0 MPC values are provided for reference only. 2.0 MPC values require immediate evaluation and action by I & C and Chemistry as they could require a four-hour NRC notification.

Readings >2MPC could result in >.2 MREM /hr. at the site boundary. If it is determined that .2 MREM /hr is exceeded, then the event requires classification per S01(23)-VIII-1.

~

UNIT 1 MONITOR READING - CPM OR uti/sec MONITOR # APPLICABILITY 2.0 MPC 1.0 MPC 0.5 MPC R-1212 Monitoring Plant 1 Fan 5.9E3 cpm 3.0E3 cpm 1.5E3 cpm Vent Stack 2 Fans 3.0E3 cpm 1.5E3 cpm 7.5E2 cpm i R-1212 Monitoring Containment 5.9E3 cpm 3.0E3 cpm 1.5E3 cpm l

for Purge (20,000 cfm)

! R-1214 Vent Stack 1 Fan 1.2E5 cpm 5.9E4 cpm 2.9E4 cpm

(1) 2 Fans 5.9E4 cpm 2.9E4 cpm 1.5E4 cpm t

R 1219 Vent Stack 1 Fan 9.lE4 cpm 4.6E4 cpm 2.3E4 cpm 2 Fans 4.56E4 cpm 2.28E4 cpm 1.14E4 cpm R-1254 Vent Stack (self correct- 4.62E4 uCi/sec 2.31E4 uCi/sec 1.16E4 uCi/sec j ing for flow)

(1) R-1214 is functional, but not operable. R-1214 should be used for comparison with other similar monitors. A reportability determination should not be based I

solely on R-1214's reading.

ATTACHMENT 2 PAGE 3 0F 5 k _ __ -

, NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 26 0F 44 ATTACHMENT 2 TCH /-a -

IV. B. (Continued) .

UNITS 2 AAD 3 MONITOR READING - CPM, uC1/sec, or uCi/cc MONITOR # APPLICABILITY 2.0 HPC 1.0 MPC 0.5 MPC 2/3 RT 7808C 1 Fan 5.2E4 cpm 2.6E4 cpm 1.3E4 cpm 2 Fans 2.8E4 cpm 1.4E4 cpm 7.lE3 cpm 2RT7818A(1) MSIV open (1000 cfm) 5.0E6 cpm 2.5E6 cpm 1.3E6 cpm 2RT 7818B(1) MSIV open (1000 cfm) 3.6E6 cpm 1.8E6 cpm 9.lE5 cpm 2RT 7865(3) 6.25E4 uCi/sec. 3.13E4 uti/sec 1.56C4 uCi/sec 2RT 7870 MSIV open 1.25E5 uCi/sec 6.25E4 uCi/sec 3.13E4 uCi/sec 2RT 7828(2) 40,000 cfm 6.62E-3 uti/cc 3.31E-3 uCi/cc 1.66E-3 uCi/cc (1.35E5 cpm) (6.76E4 cpm) (3.39E4 cpm) 2,000 cfm 1.32E-1 uCi/cc 6.60E-2 uCi/cc 3.30E-2 uCi/cc (2.69E6 cpm) (1.35E6 cpm) (6.73E5 cpm) 3RT7818A(1) MSIV open (1000 cfm) 5.7E6 cpm 2.9E6 cpm 1.4E6 cpm 3RT 7818B(1) MSIV open (1000 cfm) 2.84E6 cpm 1.42E6 cpm 7.llE5 cpm 3RT7865(3) 6.25E4 uCi/sec 3.13E4 uCi/sec 1.56E4 uCi/sec 3RT 7870 MSIV open 1.25E5 uCi/sec 6.25E4 uCi/sec 3.13E4 uCi/sec 3RT 7828(2) 40,000 cfm G.62E-3 uCi/cc 3.31E-3 uCi/cc 1.66E-3 uCi/cc (1.27ES cpm) (6.34E4 cpm) (3.18E4 cpm) 2,000 cfm 1.32E-1 uCi/cc 6.60E-2 uCi/cc 3.30E-2 uCi/cc (2.53E6 cpm) (1.26E6 cpm) (6.32E5 cpm)

(1) Setpoints may be raised as a function of ratio of ejector flow to 1,000; e.g., 1,000 cfm/20 cfm x listed setpoint = corrected setpoint.

(2) 2RT-/828 and 3RT-7828 indications are for total release from the plant, i.e., a P-factor 1.0 or zero release from the opposite unit.

(3) Each unit.Unit's 7865 setpoint assumes equal discharge is occurring from opposing Therefore, e.g., 2 MPCs equals both Units discharging at listed setpoints.

ATTACHMENT 2 PAGE 4 0F 5

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• NUCLEAR ~ GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 27 0F 44 ATTACHMENT 2 TCH /-L IV. B. (Continued)

To further amplify the previous guidelines, the following points must be emphasized:

(1) The accidental, unplanned or uncontrolled radioactive release mentioned in the guidelines is a result other than normal or expected releases from maintenance or other operational activities.

(2) The accidental, unplanned or uncontrolled radioactive release mentioned in the guidelines is either confirmed or believed to be in progress.

Finally, it must be emphasized that all unplanned or uncontrolled releases (regardless of 10 CFR 50.72 NRC reportability shall be promptly reported to HP.

and Chemistry so that in-plant radiation expos)ure and effluent assessment can made.

ATTACHMENT 2 24649 .cIn PAGE 5 0F 5 Y

• NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS GIVISION PROCEDURE S0123-0 REVISION 1 PAGE 28 0F 44 ATTACHMENT 3 TCH / w2-EMERGENCY TELEPHONE NUMBERS FOR NOTIFICATION AND REPORTING NRC Ooeratino Center.

Teleohone Number Primary: EMERGENCY NOTIFICATION SYSTEM to NRC Operations Center (Lift Receiver from Cradle)

Alternates: Commercial Telephone System to (301) 951-0550 (primary)

HRC Operations Center (301) 427-4056 (back up)

(301) 427-4259 (back up)

(301) 492-8893-(back up)

Health Physics Network to (301) 951-1212 (primary)

NRC Operations Center (301) 951-6000 (back up)

(301) 951-0550 (back up)

Operations Division Duty Manaaer Primary: J. L. Reeder PAX: 86-242 (1)(2) (UNIT 1) Home: (619) 471-0950 V. 8. Fisher PAX: 86-517 (UNITS 2 &3) Home: (714) 492-0722 Alternates: R. W. Krieger PAX: 86-255 Home: (714) 240-2694 H. E. Morgan PAX: 86-141 .

Home: (714) 837-3586 Comoliance Outy Reoresentative Primary: J. P. Shipwash PAX: 86-208 (3) Home: (619) 480-2580 R. D. Plappert PAX: 89 821 Home: (714) 661-7633 G. T. Gibson PAX: 86-135 Home: (619) 487-3523 P. C. Wattson PAX: 89-232 Home: (619) 931-0260 (1) Alternate methods to contact site personnel are as follows: Site page (86-292),

Site beeper (86-799), or Off-site beeper (PAX: 7-21-212 or (818) 302-1212).

(2) On weekends, contact the posted Operations Division Outy Manager.

-(3) Contact the posted Compliance Duty Representative.

ATTACHMENT 3 PAGE 1 0F 2

. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 29 0F 44 ATTACHMENT 3 TCN / % t EMERGENCY TELEPHONE NUMBERS FOR NOTIFICATION AND REPORTING (Continued)

NRC Resident Insoector Primary: R. Huey PAX: 86-362 (2] Beeper: 651676 Home: (714) 498-6600 III Alternates: J. Tatum PAX: 86-362 (2] Beeper: 651634 (Unit 2/3 Home: (619) 931-9147 Inspector)

A. Hon PAX: 86-362 (2] Beeper: 651708 (Unit 1 Home: (714) 492-9633 Inspector) i I

(1) Alternate NRC Resident Inspector salection should be as follows:

1 1st Alternate - Unit Inspector 2nd Alternate - Other Units Inspector (2) Personnel wishing to contact the NRC by beeper must:

1. Call page company at 714-835-1162 or 714-772-7243.

2. After a pulsing tone is heard enter the desired besper number on a touch tone phone.

3. After a second pulsing tone is heard, enter the phone number (maximum of 20 digits) which is to be called back by the owner of the beeper.

4. After a t'inal pulsing tor.e is he6rd, hang up. The residents, upon hearing their beeper, will call the phone number entered in step 3 above.

ATTACHMENT 3 24649.cin PAGE 2 0F 2

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 30 0F 44 ATTACHMENT 4 TCN /-dL OPERATIONS REPORTING RE0VIREMENTS 1.0 NOTIFICATION OF PLANT MANAGEMENT 1.1 Station Manager or Manager, Operations approval shall be obtained prior to voluntary entry into LCO 3.0.3. Such approval and entry shall be documented in the Shift Superintendent's Log.

1.2 The Shift Superintendent shall, as soon as practical, notify the Plant Superintendent or his designee, of the following conditions:

1.2.1 A Technical Specification Safety Limit is exceeded;

.1 The CDR shall also be informed to complete notification pursuant to Technical Specification 6.7.1.

1.2.2 A Technical Specification is exceeded; 1.2.3 The Emergency Plan is initiated; 1.2.4 An unplanned unit or reactor trip; 1.2.5 Any condition which cannot be corrected by the operators which may affect the plant or public safety; 1.2.6 Any event which, in the opinion of the Shift Superintendent, should be reported.

1.2.7 The content of any NRC required Notification of step 6.10.1.

1.3 Operations management should make the following reports to the Operations Manager during nonworking hours:

1.3.1 Report as quickly as practical; Use Edison page if Operations Manager is not at home:

.1 Serious injury to an operator, or to others as a result of an operating error.

.2 Any unplanned or unanticipated reduction in capacity.

.3 Non-spurious events requiring Red Phone reports.

.4 Serious noncompliance which will likely result in NRC enforcement action.

1.3.2 R.rport promptly, but do not page, do not call between 2200 dnd 0500:

ATTACHMENT 4 PAGF 1 0F 8

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 31 0F 44 ATTACHMENT 4 TCH /4 1.0 NOTIFICATION OF PLANT MANfGEMENT (Continued) 1.3.2.1 Injuries to operators, or to others as a result of operating errors that require transportation off-site for treatment.

.2 Spurious events requiring Red Phone reports.

.3 Responses to inquires from higher management or regulatory bodies.

1.3.3 Report by 0900 next day:

.1 Items "held" between 2200 and 0500.

.2 "Near miss" circumstances of interest.

. .3 Non-lcst time accident

.4 Major equipment problems.

.5 Initiation of divisional investigations.

.6 "Hands off" direction from Energy Control.

.7 Any other item considered appropriate.

NOTE: Duplicate courtesy notifications of the Plant Superintendents should be made when possible.

Direct contact of higher management should only be initiated by Duty Managers when both the Plant Superintendent and Operations Manager are unavailable. Duty Managers will respond fully to any inquiries from higher management or regulatory bodies.

2.0 NOTIFICATION OF SHIFT TECHNICAL ADVISOR (STA) 2.1 The Shift Superintendent shall ensure the Shift Technical Advisor notified of the following conditions: (Reference 2.3.8) 2.1.1 Wnenever the Plant Superintendent is notified per this attachment.

2.1.2 Operational events, including abnormal indications affecting safety systems which after immediate operator investigation:

ATTACHMENT 4 PAGE 2 0F 8

NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 32 0F 44 ATTACHMENT 4 d.g- TCN M 2.0 M lIFICATION OF SHIFT TECHNICAL ADVISOR (STA) (Continued) 2.1.2.1 Indicate the failure of any safety system component to perform its intended safety function (s); or-

.2 Are unexplained.

2.1.3 Whenever as determined by the Shift Superintendent that the assistance of the STA is desirable, including operation in Modes 5 and 6 e.g.,

.1 Failure of core residual heat removal (shutdown cooling) system operation during cold shutdown.

.2 Reactivity calculations such as shutdown margins, estimated critical rod positions, etc.

2.1.4 Any unexpected hydraulic transients having the potential to cause damage to equipment and/or associated supports / snubbers (Reference 2.3.9).

The following listings of notifications have been NOTE:

placed in this procedure to provide a centralized listing of notification requirements. In most cases these notifications and reports will be made by direction of specific procedures and/or technical specifications. Any additional notification requirements not mentioned below should be brought to the attention of the appropriate Supervisor of Coordination so that I they may be included in future revisions.

l l

l ATTACHMENT 4 PAGE 3 0F 8 L- _

, NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1- ' PAGE 33 0F 44 ATTACHMENT 4 .

TCN /  !

\

3.0 NOTIFICATION OF ENERGY CONTROL CENTER (ECC) (Reference System Operating Bulletin (S00) No. 12)

NOTES: 1. At Units 2 and 3, reports to the ECC are normally made by the Common Control Operator.

2. Refer to S0123-0-21, "Critical Components" Attachment for other items requiring ECC notification.

3.1 All incidents which have or may result in a unit being removed from the line shall be reported promptly. The following are examples:

3.1.1 Any reactor trip; 3.1.2 Any turbine / generator trip; NOTE:

Entry into a Limiting Condition for Operation (LCO) in which the shutdown requirement is less than 24 Hrs. should be reported immediately. LCOs in which the shutdown requirement is greater than 24 Hrs. should be reported 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before power reduction is required.

3.1.3 Entry into a shutdown LCO.

3.2 All incidents that result in or may cause unit restriction shall be reported promptly. The following are examples:

3.2.1 Circulating pump 0.0.S.;

3.2.2 Feedwater heater train 0.0.S.;

i 3.2.3 Significant increase in condenser backpressure (heat treat, seaweed influx, etc.);

j 3.2.4 Turbine stop valve testing.

l 3.3 Any manual change of protective devices shall be reported before the change is made. Any automatic initiation of protective devices shall be reported promptly. The following are examples:

3.3.1 Making sudden pressure relays non-automatic; NOTE: Mira Loma Switching Center should also be contacted regarding items 3.3.2 and 3.3.3.

ATTACHMENT 4 i

PAGE 4 0F 8 l

NUCLEAR GENERATION SITE OPERATION!. DIVISION PROCEDURE S0123-0 '

UNITS 1, 2 AND 3 REVISION i PAGE 34 0F 44 ATTAC$iEN1 4 TCH /SL 3.0 NOTIFICATION OF ENERGY CONTROL CENTER (ECC) (Reference System Operating Bulletin (SOB) No. 12) 3.3.2 Making line protection relays solid; 3.3.3 Initiation of line protection relays.

3.4 The following types of accidents shall be reprted promptly:

NOTE: When reporting acenants to the ECC, inform the ECC of the individu.1's name, employer, and request that the ECC immediately notify Claims / Claims Litigation or Occupational Safety &

Health division. Additionally, notify the Operations Manager promptly or during non-working hours per Section 1.3 of this Attachment.

3.4.1 Accidents involving serious injury or death of'an on duty personnel including death from natural causes; 3.4.2 Accidents to on duty personnel which require medical treatment and/or time off because of injuries; 3.4.3 Any accident resulting in personal injury, no matter how slight, to a non-employee, where Company personnel (on duty) or Company facilities, equipment or vehicles are involved.

3.4.4 Any accident involving potentially serious injury to c-duty personnel; e.g., all electrical contacts, any !ws of consciousness.

3.5 Performance Errors: Promptly report all incidents where the operation or failure to operate any switch or device results in any of the following:

3.5.1 Lines or equipment relay (Mira Loma Switching Center should al st; becontacted);

3.5.2 Violation of Accident Prevention Rules; 3.5.3 Violation of standard operating procedures; 3.5.4 Interruption to lines, stations, or customer load; 3.5.5 Injury or fatality; 3.5.6 Damage to operating equipment.

ATTACHMENT 4 PAGE 5 0F 8

l l

q* NVCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14

UNITS 1, 2 AND 3 REVISION 1 PAGE 35 0F 44 1 ATTACHfiENT 4 I TCN h. 4 3.0 NOTIFICATION OF ENERGY CONTROL CENTER (ECC1 (Reference System Operating Bulletin (SOB) No. 12) 3.6 Promptly report all information involving such items as fires, explosions, earthquakes, property damage, Tsunami waves, floods, uncontrolled esca)e of gas, oil spills, or any case of environmental imp 3ct that is li(ely to cause pchlic comment.

3.7 In the event a hazard to any line, equipment or installation is known or expected to exist or any information regarding such a hazard is received from some outside source; all immediately available facts should be reported promptly to the Switching Center concerned and/or ECC.

NOTE: If possible, it is of considerable adventage to have both the Switching Center and ECC on the phone together when a report is being made by a third person.

3.8 If any hostage is taken inside or outside the station or in the case of a bomb threat.

4.0 NOTIFICATION OF CHEMISTRY AND/OR EFFlVENT ENGINEERING 4.1 The following conditions should be reported to the appropriate chemistry personnel:

4.1.1 Any change in plant or equir. ant status which may affect olant chemistry, including but not limited to the following:

.1 Any cperational Mode Change;

.2 Any change: in Reactor power greater than or equal to 15%

. in any one nour;

.3 Any time reactor power exceeds 25% of rated thermal power

( m ondary criemistry considerations);

. .4 Any power reduction to below 25% of rated thermal power;

\

4.1.2 After ac unplanned release of radioactive material (e.g.

gas or ? quid) that may require analysis to ensure 10 CFR 20 or Tec'nical Specification limits are not exceeded; 4.1.3 Notify Effluent Engineering of effluent monitoring equipment failure.

ATTACHMENT 4 PAGE 6 0F 8

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 36 0F 44 ATTACHMENT 4 TCN ./ pt 5.0 NOTIFICA'JANS OF HEALTH PHYSICS 5.1 The follcsim should be reported to appropriate Health Physics personnel:

5.1.1 Any operational occurrence that may cause a significant change in any plant Radiation area where personnel may be working.

6.0 NOTIFICATION OF SECURITY 6.1 The following events shall be immediately reported to the appropriate security personnel.

6.1.1 Any breach of the Security Safeguards Contingency Plan reported to Operations; 6.1.2 Any bomb threat received by operations; 6.1.3 The loss of any security-related keys; 6.1.4 Any loss of security-related equipment; 6.1.5 If n hostage is taken inside or outside the Station.

7.0 NOT FICATION OF,jdE FEDERAL f.VIATION ADMINI.STRATION 7.1 Units dy only - If bAtt Aircraft Obstruction Warning Light Systems fai'. (dome lights out), then notify the Federal Aviation Administration pe S023-6-10.

8.0 8120RTS TO STATION TECHNICAL 8.1 The following events shall be reported to the appropriate Station Technical personnel:

8.1.1 Any Technical Specification Action requiring an Engineering Evaluation.

8.1.2 Any reactivity anomaly occurring during a reactor startup where, after proper investigation has been completed, results in a projected criticality greater than .5% AK/K away from the predicted point of criticality.

8.1.3 Unit 1 only - Waterhammer events in safety-related systems will be reported to Station Technical within a reasonable period.

8.1.4 Unit 1 only - Report any CHALLENGE to PORV's or block valves or pressurizer safeties to Station Technical within a reasonable period.

ATTACHMENT 4 PAGE 7 0F 8

-NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14' REVISION 1 PAGE 37 0F 44 ATTACHMENT 4 TCH / ~cL 9.0 REPORTS TO EMERGENCY PREPARE 0 NESS 9.1 The following should be reported to appropriate Emergency Preparedness personnel:

9.1.1 Any injuries to Station personnel.

9.1.2 Any reports of fire or releases of toxic gasses.

9.1.3 Any Tech. Spec. required fire equipment found or made to be inoperable.

10.0 REPORTS TO COMPLIANCE 10.1 Unit 1 only - In addition to previously noted NRC notifications, the following should be reported to Compliance:

10.1.1 Report any CHALLENGE to PORV's or block valve or pressurizer safeties to Compliance within a reasonable period.

10.1.2 Report any failure during test or operation of a Safety Injection System Hydraulic Valve (HV-851 A/B, HV-852 A/8, HV-853 A/8, or HV-854 A/B) to Compliance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Reference 2.3.5).

10.1.3 Report any instance of no Fire Suppression Water System operable to Compliance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Technical Specification 3.14).

10.1.4 Waterhammer events in Auxiliary Feedwater System will be reported to Compliance within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

11.0 BF. PORTS TO OUTAGE MANAGEMENT 11.1 During Modes 4, 5 or 6, the Shift Superintendent shall notify Outage Management of all Red Phore Reports made to the NRC to ensure they are included in the Morning Report (Reference 2.3.6).

ATTACHMENT 4 24649 .c?n PAGE 8 0F 8

' NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0l?.3-0-14 UNITS 1, 2 AND 3 REVISION 1 PAGE 38.0F 44 ATTACHMENT 5 TCN M COMMUNICATIONS SYSTEMS REPORTABILITY WORKSHEET A. If any of the following communication systems fail, ensure that at least one of the indicated backup systems is operable. If none of the indicated backup systems are operable, then the failure is reportable as a 1-hour immediate notification pursuant to 10 CFR 50.72 (b)(1)(v).

8. In addition to the backup systems below, all offsite jurisdictions can be notified by the Energy Control Center (ECC) in Alhambra. The ECC has all points of contact for the offsite jurisdictions.

C. If five or more offsite Emergency Sirens fail their annual full-scale test, then the failure may be reportable. Contact the Compliance Duty Representative (CDR) and inform him of the failed sirens. The CDR will then contact the Nuclear Affairs and Emergency Planning Group to determine if the failures aie reportable.

NOTES: 1. The ECC can be contacted either by PAX, Automatic Call Ring Down (ACRD), or the VHF/VHF Radio.

2. Pacific Bell telephone lines can either be used by dialing out from SCE PAX telephones or direct dial lines located in all Technical Support Centers and Operational Support Centers.

3. Items 2, 3 and 4 are used to contact San Diego and/or Orange Counties, who in turn notify SOES.

4. Immediately inform the Shift Superintendent. Any Red Phone out of service, whether planned or inadvertent, is reportable as a 1-hour Immediate Notification. (This does not include Red Phone Outages discovered by the NRC during their daily checks.)

System Operability Backup System Backup Operability System Operable Failed Operable Failed

1. Emergency 1. None N/A N/A Notification (NOTE 4)

System (ENS or l RED) Phone l

2. USMC Fire

1. IAT (YELLOW)

(0 RANGE) Phone Phone

2. 8 LACK Phone i

l

3. Pacific Bell (NOTE 2) l ATTACHMENT 5 l

i PAGE 1 0F 4

1

' NUCLEAR GENERATION SITE UNITS 1, 2 AND 3 OPERATIONS DIVISION PROCEDURE S0123-0-14 REVISION 1 PAGE 39 0F 44 ATTACHMENT 5 TCH / o2s COMMUNICATIONS SYSTEMS REPORTABILITY WORKSHEET (Continued)

System Operability Backup System Backup Operability System' Operable Failed Operable Failed

2. USMC Fire

4. VHF/UHF Radios (0 RANGE) Phone (Continued) 5. Teletype

6. ECC (NOTE 1)

3. State Office 1. Pacific Bell of Emergency (NOTE 2)

Services (SOES or BLUE) Phone 2. IAT (YELLOW)

Phone

3. Orange County Teletype (follow-up information)

, 4. ODAC Radio

5. ECC (NOTE 1)

6. NOTE 3

4. Inter-agency '

1. Orange County Phone IAT Teletype (YELLOW) Phone

2. Pacific Bell (NOTE 2)

3. ECC (NOTE 1)

5. USMC Base Phone

1. IAT (YELLOW) l (BLACK) Phone Phone

2. Pacific Bell (NOTE 2)

3. UHF/VHF Radios l

j.

4. Orange County Teletype

5. ECC (NOTE 1)

ATTACHMENT 5 PAGE 2 0F 4

. NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 UNITS 1, 2 AND 3 REVISION 1 OAGE 40 0F 44 ATTACHMENT S TCN /~4 COMMUNICATIONS SYSTEMS REPORTABILITY WORKSHEET (Continued)

System Operability Backup System Backup Operability System Operable Failed Operable Failed

6. Plant Public 1. UHF/VHF Address ~ Radios

2. PAX

3. Ivory Phone

7. Pacific Bell 1. IAT (YELLOW)

Phone

2. UHF/VHF Radios

3. PAX /ECC (NOTE 1)

8. Orange County

1. IAT (YELLOW) .

Teletype Phone

2. Pacific Bell (NOTE 2)

3. UHF/VHF Radios

4. ECC (NOTE 1)

9. ODAC (BEIGE) 1. PAX .

2. 00AC Radio

3. IAT (YELLOW)

Phone

4. Ivory Phone

5. Teletype ATTACHMENT 5 PAGE 3 0F 4

NUCLEAR GENERATION SITE OPERATIONS DIVISION PROCEDURE S0123-0-14 VNITS 1, 2 AND 3 REVISION 1 PAGE 41 0F 44 ATTACHMENT 5 TCN Z @

COMMUNICATIONS SYSTEMS REPORTABILITY WORKSHEET (Continued) i System Operability Backup System Backup Operability l System Operable Failed Operable Failed 1

10. Plant Emergency 1. PAX  !

Response

(PERT or IVORY) 2. IAT (YELLOW)

Phone Phone

3. UHF/VHF Radios

4. Pacific Bell (NOTE 2)

11. Perimeter 1. Radio - Park Announcing Service System

2. Pacific Bell (NOTE 2)

3. Yellow Phone

12. PAX (for 1. IAT (YELLOW) failure, all Phone indicated backups are

2. ODAC (BEIGE) required) Phone

3. Ivory Phone

4. UHF/VHF Radios

13. Health Physics 1. Pacific Bell Network (GREEN) (Note 2)

Phone -

2. Emergency Notification System (RED)

Phone ATTACHMENT 5 24649 .cin PAGE 4 0F 4

NUCLEAR CFNERAf!CN SifE VerliS 1, 2 AND 3 OPERAf!ONS DIVISION PROCEDURE S0123 0 14 REVISION

- ^

PAGED /1 0F $l NUCLEAR REGULATORY CCMMISSION EVENT NOT!FICAfl04 FORM Ak0 LOCAL 0FFSITE AGENCY FOLLCV UP NOT!8tCATION (FUN)

N2tiflCation IiFe NRC Contact Facility / Unit Caller's Name/ fitte fetephone Ntreer (For call back)

San Onofre Unit (s) (San Onofre) 1 2 3 (circle one)

EVENT CLAS$1FICATION Y lN EVENT CATAGORY INIflAfl0N $1CNAL CAUSE OF FAILURE GENERAL EMERGENCY REACTOR TRIP / SCRAM MECHANICAL, SITE AREA [MERGENCY OTHER ELECTRICAL ALERT ECCS ACTUAfl0N PERSONNEL ERROR UNUSUAL EVEN* SAFETY INJECTION FLOW PROCEDURE !NADECUACY IHR 4HR 50.72 JON EMERGENCY LCO ACIl0N STATEMENT OfMER IMR 24NR SECUR TY/ SAFEGUARDS ESF ACTUAfl0N ESF ACTUAfl0N SPURICUS Y N TRANSPOR14fION EVENT SYSTEM:

EVENTf!ME/ ZONE EVENT DATE MONTH DAY ofMER: COMPONENf:

l l EVENT DESCRIPfl0N: (Surnary Section 1 Teletype FUN Form)

1. Current Plant Conditions (paragraph 1, 1stetype FUN)

2. Prognesis of Erergency (peragraph 3, Teletype FUN)

3. Request for Support (paragraoh 5, teletype FUN)

A00lf!ONAL QUESf!ONS FROM THE WRC AND ANSVERS GIVEN:

(Par: graph 1, Teletype FUN)

POWER PRIOR TO EVENT (%): Did att systems f a tion as equired? YES If NO Explain above.

CCRENT POWER OR MCOE: Anything aunususta or not un k .'tood? No if YES, Explain above.

OUTSIDE ACENCY OR PERSONNEL CORRECTIVE ACTION (S) ParagracA 4 (teletype FUN)

N0f!FIED BY LICENSEE STATE (S):

LOCAL:

tac RESIDENT Y W WILL SE OfMER:

LOTE! FOR A00lfl0NAL CCNutkis ON ANY SECTION, USE CONTINUAtl0N $NEET, PACE 3 0F 3 0F THIS AffCHMENT.

emn_.o

NUCLEAR CcNERAfl04 $1TE GlTS 1, 2 AND 3 OPERATIONS OlVISION PROCEDURE S0123 0 14 REVISION PAGE4]CF$f

• ATTACHMENT 6 TCN /~A A00lil0NAL INFORMAfl0N FCI RA010 LOGICAL RELEASES LIQUID RELEASE PLANNED SOURCE (S)

GASEQUS RELEASE UNPLANNE0 RADIAtl0N LEVELS IN PLANT:

RELEACI RATE (Ci/sec): EST TOTAL ACTIVITY (Cl):

RELEASE DURATICN: EST TOTAL IODINE (Cl):

RELEASE MONITORED Y N f.S. Limits: GRAS SAMPLE IELEASE FILTERED Y N .

MONITOR READING Arcas Evacuated ? Y N List below Persomel exposed /contarnination Y N Describe below Plant Mealth Physics backte requested ? Y N ADDITIONAL INFORMAfl0N:

(Section 2 Recomended Protective Actions)

DOSE PROJECTIONS / MEASUREMENTS (SECTION 6 TELETYPE FUN FORM)

DOSE RATES VNOLE SCCY TNYR010 SITE BOUNDARY (EA8) 1 MI 2 MI 3 MI 10 MI AFFECTED SECTORS: / /

METEOROLOGY DATA (SECTION 7 TELETYPE FUN F00M) STABILITY CLASS:

VINO O!RECTION (Frcrn): DEGREES TRUE VIND SPEED (tnph):

A00lfl0NAL INFORMATION FOR REACTOR COOLANT or $fEAM GENERATOR TUPE LEAKS SUDDEN OR LONG TERM DEJLOPMENT ? START DATE: START flME:

LEAK RATE: PRIMARY COOLANT ACTIVITY: MONITOR READINGS LEAK YOLUME: SECONDARY COOLANT ACflVITY: CONOENSER:

T.S. Limits: MAIN STM LINE:

SG SLOWOOW:

LIST OF SAFETY RELATED EQUIPMENT EN OPERAfl0NAlt STECIAL ACTIONS TAKEN SY LICENSEE (If any):

(TELETYPE FUM FORM SECTION 4 FOR SGTR OR RCS LEAK)

N0ft: FCR ADDITIONAL CCs**ENTS ON ANT SECTION, USE CONTINUAfl0N Sw(ET, PACE 3 0F 3 0F TNIS ATTACNMENT.

File Olsposition: After review by the Plant Superintendent. *he original shall be sent to COM and a copy sent to Ccrpliance.

AIIMlD

~

t t

%d:CE& ARC 6NERAfl0N $1TE

'M r5S11,2;AND 3 OPERAtt0NS OlVISION PROCEDURE S0123 0 1!.

REVISION

• AffACHMENT 6 f

PACEltfCF4Cf TCN /~ b NUCLEAR REGULATORY CCNNISSION EVENT NOTIFICATION F094 AhD LOCAL OFFSifE ACENCY F0ttCV UP N0ftFICAftCN (FUN)

CC6f f EW4f C4 SWEET ans m

/

ATTACMMENT 6

.N