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Latest revision as of 11:24, 15 March 2020
ML20010G951 | |
Person / Time | |
---|---|
Site: | Point Beach ![]() |
Issue date: | 09/14/1981 |
From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
To: | Harold Denton Office of Nuclear Reactor Regulation |
References | |
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-1.A.1.1, TASK-TM NUDOCS 8109220705 | |
Download: ML20010G951 (137) | |
Text
,
4 Wisconsin Electnc POWER COMPANY 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201 September 14, 1981 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION D
. Washington, D. C.
Dear Mr. Denton:
20555
[@(M 4~ ;-. .
DOCKET NOS. 50-266 AND 50-301
)Q RESPONSE TO NUREG-0737 s UPDATE TO SCHEDULE REQUIREMENTS AND IMPLEMENTATION STATUS / ,g g \s'e This letter provides additional information related to the require-ments of NUREG-0737, " Clarification of TMI Action Plan Requireinents", for the Point Beach Nuclear Plant, Units 1 and 2. This information includes Revision 2 to our Schedule Table and Notes which provides schedule and implementation status, as of September 14, 1981. Each item is addressed relative to the requirements and schedules stated in NUREG-0737 with clarification provided for those items completed, updated, or otherwise modified since our March 31, 1981 response. Your review of this response should be made with reference to prior Wisconsin Electric Power Company submittals. We have not repeated the pertinent notes referenced in the Schedule Table for those items whose status has not changed since our December 23, 1980 and March 31, 1981 submittals.
Additional attachments to the Schedule Tame and Notes are included with this submittal.
r The total scope of work involved in the TMI backfit effort is not
! always apparent from a list of schedule commitments. It does not show the effort involved to properly plan and schedule the implementation of all the items. There are many major projects that are being implemented at the same time in order to accomplish the required plant modifications. Some of these are as follows:
i 1. Purchase of about 200 new or replacement instruments to implement the TMI requirements, environmental qualification requirements, and Regulatory Guide 1.97 requirements.
j 2. Electrical changes in containment require additional new containment l penetrations.
i
- 3. A total of thirteen new instrument racks are needed to process tne new instrumentation signals.
hOY[ K 8109220705 810914 /
DR ADOCK 0500
I Mr. H:rolet R. D;,nten -Siptember 14, 1981 l
- 4. Racks must be located in a qualified area with acceptable cable
, routing capability.
- 5. Power supply requirements to new equipment and other design considera-tions require-two new station vital batteries. Associated work 2
involves procurement of batteries, three chargers, six inverters, i
various distribution panels and construction of two~ battery rooms
, and two equipment rooms.
- 6. Displays and controls must be integrated into the control room.
.: Two 15-foot long Auxiliary Safety Instrumentation Panels (ASIP) are
- required in the control room.
! 7. Operator and human factor considerations require evaluations'as to proper location of each display and control. The result is indicators being added to every panel of the control board.
- 8. To make room for the ASIP panels and meet new requirements, the present radiation monitoring system must be replaced.
- 9. A new radiation monitoring system must-be designed, procured, located and installed.
L 10. Technical Support Center instrumentation and Safety Parameter Display System (SPDS) must be factored into the plant changes.
I- 11. Fire detection system design and installation must be factored in'o the plant changes.
- 12. - Meteoro'ogical data requirements and emergency plan considerations
,! must be factored into the plant changes.
- 13. Emergency response facilities and requirements must be factored i
into the plant changes.
- 14. A new computer' system must be designed, procured and installed ;
' which integrates items 9 through 13 and results in an improved monitoring and display of plant process variables while meeting new NRC requirements.
l
! 15. For all of these changes', about 30,000 feet of conduit and 300,000
- - feet of-cable will be installed.
-16. .. Throughout all these changes,.the operators must safely operate the
- plant while coping with retraining, relicensing, changing emergency operating procedures'and changing emergency planning procedures.
The schedules given for each item listed in the attached Schedule Table are our best estimates for proper installation or completion. -The 3
schedule dates reflect our best' efforts to coordinate the large number'of
! interrelated items to ensure that they become improvements to our operating i ,
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r e
Mr. Hirold R. Denton Sept mb2r 14, 1981 plant. Arbitrarily scheduling one item ahead of another may disrupt the overall plan, cause wasted effort, and possibly result in delays to other items or final implementation of that item. A review of cs" commitments and magnitude of work in progress will demonstrate that we are attempting to implement NUREG-0737 requirements, in a very careful and deliberate manner that meaningfully improves the operation of th'.e plant. Revisions to our schedule would remove some of the benefit we are trying to achieve by proper planning.
The statement made in the abstract of SECY-81-437, Report On A Survey By Senior NRC Management To Obtain Viewpoints On The Safety Impact Of Regulatory Activities From Representative Utilities Operating and Constructing Ncclear Power Plants, July 1, 1981, applies directly to the TMI backfit schedule, i.e. , "the pace and nature of regulatory actions have created a potential safety problem which deserves furti.er evaluation by the agency." We believe that the schedule listed in the attached Schedule Table allows us to deal properly with the many difficult technical issues listed in the executive summary of SECY-81-437, e.g. , proper control of the large number of workmen in an operating plant, proper management of resources and priorities, allowance for coordination of the various requirements, minimum impact on plant operating staff, allowance for orderly transition and training, and focus of attention on primary areas of responsibility.
We would be pleased to respond to any questions you may have regarding the schedule or the attached technical mr.orial.
Very truly yours, O
h w /j ' :' -
a f
Sol Burstein Execu ive Vice President Enclosures Subscribed and sworn to before me
~
thi 14th -September, 1981 CW"14 . Y^7') Y Notary Public, State of Wisconsin f My commission e es ///M#4[
Copy to NDC Resident Inspector
s
, n RESPONSE TO NUREG-0737 POST-TMI REQUIREMENTS 4
FOR OPERATING PLANTS i
J I
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-266 and 50-301 Schedule Table and Notes Revision 2 - September 14, 1981 1
~
POST-THI REGUIREMENTS FOR OPERATING REACTORS J
NRC "
Cirriff- Implemen- PBNP cation tation Applica- PBNP Item Sh'.rtened Title Description 3chedule bility Schedule Remarks I. A.1.1 Shift Technical Advisor 1. On duty 1/1/80 Yes Completed On duty since 1/1/80 - Reference 1 and 12a
- 2. Tech Specs 12/15/80 Yes Completed Referenc2 12a and 15
- 3. Trained per LL Cat B 1/1/ft Yes Completed Note I.A.1.1.3
- 4. Describe long-tern Ic 1/1/81 Yes Completed Reference 17 program ,
I.A.1.2 Shift Supervisor Delegate non-safety 1/1/80 Yes Completed Reference 1 Responsibilities duties .
- I.A.I.3 Shift Mannlig 1. Limit overtime 11/1/80 Yes Completed PBNP Approved Procedure 4.3, Operations (Reference 4a) (1/10/81 Division Personnel Assignments and 2 Implementation Scheduling, Rev. 0 Date)
- 2. Min. Shift Crew 7/1/82 Yes N.A. Note I,A.1.3.2 I.A.2.1 Immediate Upgrading of 1. SRO Experience 5/1/80 Yes Completedl R0 and SRO Training and 2. SR0s be R0s 1 yr. 12/1/80 Yes Completedt 2 Qualifications 3. Three no. training 8/1/80 Yes Completed ( Note I.A.2.1.1/4 on shift Reference 9a -
- 4. Modify training 8/1/80 Yes Completed;
- 5. Facility Certification 5/1/80 Yes Completed Note I.A.2.I'5 I.A.2.3 Administration of Training Instructors Complete 8/1/80 Yes Completed, Note I.A.2.3 Programs SRO Exam I.A.3.1 Revise Scope and Criteria 1. Increase scope 5/1/80 Yes Completed for Licensing Exams 2. Increase passing grade 5/1/80 Yes Completed
- 3. Simulator exam 6/1/80 N.A. ---
Vote I.A.3.1.3 N. A. = Schedule not applicable to PBNP TBD = To be determined at a later date per the remarks .
(1) = Revision 1 dated March 31, 1981 (2) = Revision 2 dated Septem>er 14, 1981.
e i
w
NRC Cirrift- Implemen- P8NP cititn tation Applica- PBNP Item Shortened Title Description Schedule bility (chedule Remarks ;
I.C.1 Short-Tern Accident and 1. 58 LOCA 6/1/80 Yes Completed Procedures Revisd 2. Inadequate Core Cooling
- a. Reanalyze and 1/1/81 Yes Completed Ceneric procedures already submitted -~
g propose guidelines to NRC - Reference 26
- b. Revise procedures First Yes 12/31/82 Note I.C.1 refueling 2
cutage after 1/1/82
- 3. Transients and accidents - -
- a. Reanalyze and 1/1/81 Yes Completed .
l1 propose guidelines
- b. Revise procedures First Yes 12/31/82 Note I.C.1 refueling - l2 outage after ,
1/1/82 ,
I.C.2 Shift anu Relief Turnover Implement shift turnover 1/1/80 Yes Completed Reference ~9b 2
Pro edures check 11st I.C.3 Shift-Supervisor Clearly define superv 1/1/80 Yes Completed Responsibility and oper responsibilities ,
I.C.4 Control-Room Access Completed Reference 9b Establish authority limit 1/1/80 access Yes l2 I.C.5 Feedback of Operating Licensee to iglement 1/1/81 Yes Completed PBN/ Administrative Procedure 3.15.7, procedures (1/1/81 Rev. O, arproved 12/19/80, " Procedure for Effective Date) Feedback of Operating Experience to Plant Staff" I.C.6 Verify Correct Performance Revise performance 1/1/81 Yes Completed PRNP Administrative Procedure 4.13, Rev. 9, of Operating Activities procedures et~ active 6/20/80, " Equipment Isolation Procedure" (1) = Revision 1 dated March 31, 1981 (2) = Revision 2 dated September 14, 1981 .
-V
- _ _ __ _ -__ __s
NRC Citrift-Implemen- P8NP c tion tation Applica- P8HP J Item Shortened Title Description Schedule bility Schedule Remarks I . D.1 Control Room Design Preliminary assessment TBD Yes TBD Note I.D.1 Reviews and scheduld for correcting deficiencies l2
, I.O.2 Plant Safety Parameter 1. Description Display Console TBD Ye t Completed 1
- 2. Insta11ed TBD Yes S/1/83 % Note I.D.2 2 (Projected)
- 3. Fully implemented T80 Yes 9/1/83
~
(Projected)
- 11.8.1 Reactor Coolant Sysise 1. Design vents 7/1/81 Yes Completed]
Vents 2. Install Vents 7/1/82 Yes 12/1/82 > Note II.8.1 (LL Cat B) ' .
- 3. Procedures 1/1/82 Yes 3/1/82 .s II.8.2 Plant Shielding 1. Review designs 1/1/80 Yes Completed
- 2. Plant modifications 1/1/82 Yes 9/1/82 Note II.B.2.2 :
(LL Cat 8) l1
- 3. Equipment qualification 6/,30/82 Yes 6/30/82 Note II.8.2.3 2
, II.B.3 Post Accident Sampling 1. Interim system 1/1/80 Yes Completed
- 2. Plant modifications 1/1/82 Yes 1/1/82 Note II.8.3 II. 8. 4 (LL Cat 8) Reference 29 g l2
- Training for Mitigating 1. Develop training 1/181 Yes Completed Core Damage program
- 1
- 2. Implement program
- a. Initial 4/1/81 Yes Completed Note II*8*4 12 '
- b. Complete 10/1/81 Yes 10/1/81 I
i (1) e Revision 1 dated March 31, 1981 (2) = Revision 2 dated September 14,1981 e
e i
NRC Citrift- Implemen- PBNP ,
cation tation Applica- PBNP ltem Shortened Title Description Schedule bility Schedule Remarks II.D.1 Relief and Safety Valve 1. Submit program 1/1/80 Yes Completed Reference 10a Test Requirements 2. RV and SV Testing (LL Cat B)
- a. Complete testing 7/1/31 Yes 6/30/827
- b. Plant-specific 10/1/81 Yes $5/1/82 f Note II.D.1.2 2 report
- 3. Block-Valve testing 7/1/82 Yes M.A. Note II.D;1.3 II.D.3 Valve Position Indication 1. Install direct 1/1/80 Yes Completed Note II.D.3.1 i
indications of valve Reference 9b ~
1 valve position
- 2. Tech pecs 12/15/80 Yes Completed Reference 15 1
II.E.1.1 Auxiliary Feedwater System 1. Short ters 7/1/81 Yes TBD 1 Note II* E,1*1 Evaluation 2. Long ters 1/1/82 Yes TBD J 4 II.E.1.2 Auxiliary Fe.edwater System 1. Initiation Initiation aad Flow a. Control grade 6/1780 Yes N.A.
- b. fafety grade 7/1/81 Yes Original References 1, 2, 3, and 12a Plant Design
- 2. Flow Indication
- a. Control grade 1/1/80 Yes Completed Note II.E'..).2
- b. LL A Tech Specs 12/15/80 Yes Completed Reference 12a and 15 .~ 1
- c. Safety grade 7/1/81 Yes 8/1/81 II.E.3.1 Emergency Power for 1. Upgrade power 1/1/80 Yes Original References 1, 2, 1 and 12a Pressurizer Heaters Plant Design
- 2. Tech Specs 12/15/80 Yes Completed Reference 15 l1 II.E.4.1 Dedicated Hydrogen 1. Design 1/1/80 Yes Original References 1, 2, and 3 Penetrations Plant Design
- 2. Install 7/1/81 Yes N.A.
(1) = Revision i dated Narch 31, 1981 (2) = Revision 2 c;ated September 14, 1981
d NRC ;
Citriff- Implemen- PBNP cction tation Appitca- PBNP Item Shortened Title Description Schedule blitty Schedule Remarks II.E.4.2 containment Isolation 1-4. Imp. diverse 1/1/80 Yes 6/1/83* Note II.E.4.2.1/4 Dependability 2 isolation
- 5. Cntet pressure setpoint
- a. Specify 1/1/81 Yes Completed Reference 42 pressure l l 2
- b. Modifications 7/1/81 Yes N.A.
- 6. Cntet purge valves 1/1/81 Yes Completed Administrative 1y closed - Reference 45 *
- 7. Radiation signal on 7/1/81 Yes Original Reference Point Beach FFDSAR Section 4.2 purge valves Plant Design and Figure 5.2-8
- 8. Tech Specs 12/15/80 Yes Completed Reference 15 l1 i II.F.1 Accident Monitoring 1. Noble gas monitor '1/1/82 *
- 2. Iodine / particulate Yes 5/1/82*1 Note II.f.1.7/2 2 1/1/82 Yes 5/1/82* J sampling .
l1
- 3. Containment high- 1/1/82 Yes 10/1/82* Note II.F.1.3 8 range radiation monitor
- 4. Containment pressure 1/1/82 Yes 10/1/82* Note II.F.I.4
- 5. Containment water 1/1/82 Yes 10/1/82* Note II.F.1.5 t
level .
- 6. Containment hydrogen 1/1/82 Yes 12/1/82* Note II.F.1.6 II.F.2 Instrumentation of 1. Subcool meter 1/1/80 Yes Completed Note II.F'.2.1 1,6 Detection of Inadequate 2. Tech Spec 12/15/80 Yes Completed Reference- 15 l
Core Cooling (LL Cat A) *
- 3. Install level 1/1/82 Yes 12/1/82* Note II.F.2.3 instruments ( 2 (LL Cat B) j II.G.1 Power Supplies for 1. Upgrade to energ 1/1/80 Yes Original Reference 12a 2 Pressurizer Relief Valves, sources Plant Design l Block Valves, and Level - 2. Tech Specs 12/15/86 Yes Completed Reference 15 Indicators .
l 1 a
a Schedule is based on delivery of equipment on schedule.
(1) = Revision 1 dated March 31, 1981.
(2) e Revision 2 dated September 14, 1981 n
NRC .
Implemen- J Clarlft-Cat 1on tat 1on ApplIca- PBNP ,
Item Shortened Title Description Schedule bility Schedule Remarks ,
II . K.1 IE Sulletins 79-05, -06, -08 Bulletin Yes Compieted Reference 33 l2 specific II.F 2 Orders en 8&W Plants 8. Upgrade AFW system See II.E.1.1 N %. ---
- 10. Safety grade trip 7/1/81 N.A. ---
- 11. Operator training, Complete N.A. ---
dr1111og
- 13. Thermal-mechanical 1/1/82 Yes 1/1/82 Note II.K.2.13 report
- 15. Effects of slug flow Completed N.A. ---
on OTSGS l 16. RCP seal damage Completed N.A. --- -
- a. Complete '---
- 17. Volding in RCS N.A.
- b. 1/1/82 Yes 1/1/82 Note II.K.2.17
- 19. Benchmark analysis b Complete N.A. ---
l2 of seq. AFW flow b. 1/1/82 Eliminated N.A. Reference 34
- 20. System response to Complete M.A. ---
58 LOCA II.K.3 Final recommendations, 1. Auto PORV isolation -
840 Task Force a. Design 7/1/81 Yes N.R. ,
- b. Test / install 1st refueling Yes N. R. Note II.K.3.1 and Reference 4 l1 6 mos after -
staff approval
- 2. Report on PORV failures 1/1/81 Yes Completed Note II.K.3.2 l1
- 3. Reporting SV and RV 1/1/81 Yes Completed Note II.K.3.3 l1 failures and challenges
- 5. Auto trip on RCPS
- a. Propose modifications 7/1/81 Yes TBD
}*
- Note II.K.3.5 l2 .
- b. Modify 3/1/82 Yes TB0 ,,1 N.R. = Not Required (1) = Revision i dated March 31, 1981 (2) = Revision 2 dated Septeelher 14, 1981 e
m/ g d
i NRC ,
~
Citriff- Implemen- PBNP cititn tation Applica- FBNP Item Shortened Title Description Schedule bility Schedule Remarks.
II.K.3 Final recommendations, 7. Eval of PORV opening 1/1/81 N.A. ---
(Continued) B&O Task Force probability
- 9. PIO contre 11er 1/1/81 Yes Completed Controller change made upon initial notification by vendor prior to TNI-2 2
(References 4 and 43)
- 10. Proposed anticipatory Plant Yes Original References 4 and 43 trip modifications specific Plant Design
- 11. Justify use of Plant Yes N.A. As part of the original Plant design certain PORV specific (different from TNI-2), Point Beach has i
Copes-Vulcan PORVs which corresponds to the Westinghouse esta base, and, thus, no justification is needed.
- 12. Anticipatory trip on ,
- a. Confirmation or 1/1/81 Yes Original Reactor trip caused by turbine trip proposed Plant Desgn bypassed below SCE power as detected by modifications the power range detectors. (Reference 43) 2
- b. Modi fy 1st refuel N. A. ---
60 mo. after staff approval
\
- a. Analysis 1/1/81 N.A. --- '
- b. Modify 7/1/81 N.A. --- . .
- 14. Iso condenser isol 1/1/82 N.A. / --- *'
modification
- 15. Isolation of HPCI and 7/1/81 N.A. ---
RCIC modification
- 16. Challenges end failures to relief -
valves
- a. Study 4/1/81 N.A. ---
- b. Modify 1st refueling N.A. ---
or 1 yr after approval .
(1) a Revision 1 dated March 31, 1981 (2) = Revision 2 dated September 14, 1981
. +
t
d
^
i N4C J Clariff- Implemen- P8NP ,
cGtion tation Applica- P8NP Item Shortened Title Description Schedule bility Schedule Remarks' ,_
II.K.3 Final recommendations, 17. ECCS system outages 1/1/81 Yes Completed Note II.K.3.17 - Reference 23 1,2, (Continued) B&O Task Force .
- 18. ADS actuation
- a. Study 4/1/81 N.A. ---
- b. Propose mods 4/1/82 N.A. ---
- c. Modification 1st refuel N.A. ---
6 no after staff approval
- 19. Interlock rectre pump 7/1/81 N.A. ---
modification
- 20. Loss of SVC 7/1/81 N.A. ---
- 21. Restart of CCS and .
LPCI 4
- a. Design 1/1/81 N.A. ---
- b. Modification 1st refueling N.A. ---
60 mo after staff approval
- 22. RCIC suction
- a. Verify procedures 1/1/81 N.A. ---
- b. Modification 1/1/82 N.A. ---
- 24. Space cooling for 1/1/82 N.A. ---
HPCI/RCIC modifications s _
, 25. Power on pump seals
- a. Propose mods 1/1/82 Yes- 1/1/82
- b. Modification 7/1/82 Yes N.A. Note II.K.3.25
- 27. Com ref level 7/1/81 N.A. ---
- 28. Qual of ADS 1/1/82 N.A. ---
. 29. Performance of 4/1/81 N.A. ---
isolation condensers
- a. Schedule outline 11/15/80 Yes TBD
- b. Nodel 1/1/82 Yes T80 Note II.K.3.30
- c. New analyses 1/1/83 or Yes TBD 1 yr after
- staff approval 1
(1) = Revision 1 dated March 31, 1981 j (2) o Revision 2 dated Septembpr 14, 1981 e .
s
a.
NRC a Clarif1- Implemen- PBNP c'.tlon tation Applicab- PBNP -
Item Shortened Title Description Schedule bility Schedule Remarks-II.K.3 Final recommendations, 31. Compliance with 1/1/83 or Yes TBD Note II.K.3.31 (C:ntinued) B&O Task Force CFR 50.46 1 yr after staff approval
- 40. RCP seal damage See II.K.2.16 N.A. ---
- 43. Effects of slug flow See II.K.2.15 N A. --- -
- 45. Manual depressurization 1/1/81 H.A. ---
i 46. Michelson concerns' Completed N.A. ---
III.A.1.1 Emergency Preparedness, Short-term improvements Completed Yes Completed Short Tern -
4 III.A.1.2 Upgrade Emergency Support 1. Interim TSC, OSC and 1/1/80 Yes Cos:pleted Note III.A.1.2 Facilities EOF l 1,9 Reference 9b
- 2. Design Reference 15b Yes Completed
~
Reference 28
- 3. Modifications Reference 15b Yes 2/1/82 Reference 13, 28 and 38 l2 III.A.2 Emergency Preparedness 1. Upgrade .:mergency 4/1/81 Yes Completed Note III.A.2.1 -
l 1,8 plans to App. E. Reference 12b and 17a 10 CFR 50
- 2. Meteorological data 6/1/83 Yes TBD Note III A.2.2 - References 13, 28 and 38 l 1,6 III.D.1.1 Primary Coolant Outside 1. Leak reduction Completed Yes Completed Currently changing to a yearly testing Containment schedule for both units coincident with
- 2. Tech Specs refueling outages (References 1. 2, and 3) 12/15/80 Yes Completed Reference 15 l1 III.D.3.3 Inplant Iodine Monitoring 1. Provides means to Completed Yes Completed Reference 12a determine presence of l2 radiofodine
- 2. Modifications to 1/i/81 Yes Completed Note III.D.3.3 - Reference 12a l 1,2 accurately measure 1 2
III.D.3.4 Control Roon Habitability 1. Review 1/1/81 Yes Completed Note III.D.3.4
- 2. Modification 1/1/83 Yes 1/1/83 Note III.D.3.4 lji (1) = Revision 1 dated March 31, 1981 (2) = Revision 2 dated Spptember 14, 1981 D
g .
I I 0
Revision 2 9/14/81 I.A.1.1.3 SHIFT TECHNICAL ADVISOR TRAINING Shift Technical Advisor vaining was completed prior to the Marcn 1,1981 commitment (Reference 5) as described in the attachments to Reference 17, with the exception of training for mitigating core damage as addressed in II.B.4. Shift Technical Advisory training to meet the requirements of NUREG-0737 is therefore considered completed for the Point Beach Nuclear Plant Duty and Call Technical Advisors (DCTA's).
I.C.1 SHORT-TERM ACCIDENT AND PROCEDURES REVIEW The program to achieve compliance with NUREG-0737, Item I.C.1, was presented to the NRC in a meeting held a June 18, 1981, and submitted to the NRC by Owners Group letter, OG-61, dhted July 7, 1981, R. W. Jurgensen to S. H. Hanauer (Reference 36). The previous program submittal to the NRC (Reference 20) resulted in several basic concerns which could not be easily resolved within the scope of the material submitted. These NRC concerns and me need to better organize the set of emergency procedures resulted in a new configura-tion which was presented to the NRC at the June 18, 1981 meeting. Owners Group letter OG-61, Reference 36, requested that an NRC response be received by August 1 in order to allow timely implementation of the procedures program.
As of this writing, the NRC has not re.*ponded to that request. Due to this lack of NRC response, and what appoi.'s ".o be a developing relationship between SPDS, control room review and proceduies, a specific commitment to complete the procedures effort cannot be defined at this time. If the procedures ef fort only consists of organizing and rewriting the emergency procedurcc consistent with the program described in 0G-61, this can be completed before the end of 1982. If other related efforts are required, e.g., control room review, a revised schedule will have to be determined. The requirements for emergency procedures as described in NUREG-0799, if fully implemented, will extend this effort into 1982. Comments on NUREG-0799 were provided in C. W. Fay to Secretary of the Commission letter dated August 25, 1981 (Reference 44).
I.D.1 Control Room Design Reviews t The control room design review requirements as defined in NUREG-0700 and l NUREG-0801 have not been issued in their final form as of this writing; nor I
has a schedule for completion been established by the NRC. In addition, l NUREG-0799 states that the design of the SPDS, control room review and procedures should be performed in consideration of each other. This is a l principle we endorse because we have tried to apply this to all of the TMI l backfit items as well as our preliminary review of Regulatory Guide 1.97. We will inform the NRC of our schedule when all the requirements have been issued in final form.
I.D.2 21 ant Safety Parameter Display Console Two projects are underway that relate to the safety parameter display console.
The first project is a joint effort with eleven other utilities and Quadrex I
Corporation to design a Safety Assessment System and demonstrate its effective-ness. This group of utilities met with the NRC on May 14, 1981 for the l
i Revision 2 9/14/81 purpose of describing the program and showing some of the detailed informa-tion about the project. The presented material was submitted to the NRC via Ward Wogsland to Leo Beltracchi letter dated May 19, 1981 (Reference 26a).
The second project deals with the procurement and installation of the hardware l
system. Wisconsin Electr ic on August 24, 1981, signed an agreement with
- Electronics Associates, Inc. (EAI) for the suppit of a computer system and
- associated software on which to implement the safety parameter display console.
The description of these two projects was submitted to the NRC as Attachment "C" from Sol Burstein to H. R. Denton letter dated June 1, 1981 (Reference 28). The implementation of the NUREG-0696 requirements and our position on Regulatory Guide 1.97 were also included in that submittal (Reference 28).
The schedule for installation and initial operation of the SPDS is projected to be May of 1983. The system should be fully implemented by September of r 1983. The schedule requires a few additional months because the computer !
l system purchased from EAI to implement the SPDS will replace the presently installed plant computer and will be performing all of process computer
! functions as well as providing the total data base to the Technical Support l Center.
II.B.1 REACTOR COOLANT SYSTEM VENTS - DESIGN The Point Beach reactor coolant system gas venting systems were purchased from Combustion Engineering. The system design is shown in the attached schematic and provides for parallel vent paths from both the reactor vessel head vent and/or the pressurizer steam space to the pressure relief tank (PRT) and/or containment atmosphere. The parallel paths ensure vent capability from both vessels even considering a single failure. Each path is provided ,
! with an orifice to limit flow in the event of a downstream leak or break.
l The orifice size is 7/32" diameter. Leakage through a hole this size (<3/8" i diameter) is within the capability of makeup fror. the charging system. The isolation valves used are pilot-operated Target Rock solenoid valves which fail closed. A solenoid valve in each vent path provides series valving to ensure isolation. Appropriate manual isolation, vent, drain, and test connection valves are provided to permit en-line maintenance, meet all testing requirements and allow flexibility.
Power for the solenoid valves will be obtained from 125V DC safety grade busses normally supplied by a charger with battery backup. Two busses will be used for the gas vent system solenoid valves with one aus supplying power to one valve in each vessel vent path and one series vent valve. The other bus will supply the other (parallel) vessel vent valve and the other series vent valve. A loss of either power supply does not prevent venting of either vessel.
The connecting piping between the reactor vessel head vent and the pressurizer steam space vent will provide a continuously sloped path which allows for gas (steam) venting from the vessel to the pressurizer.
, Redundant, direct position indication is available for each solenoid valve.
Single indication will be provided since separation cannot be assured (magnetic reed switches in the solenoid housing).
l Revisien 2
, 9/14/81 A wide-range pressure transmitter will be connected to the manifold of piping which connects to each solenoid valve. This will allow nonitoring of the system for leaks and during operation. The transmitter signal will be processed in the Foxboro Spec 200 racks. All controls and indications will be in the control room on the ASIP.
Installat'7n of the gas vent system will require a cold shutdown of each unit for access to the reactor vessel head, refueling cavity, and pressurizer.
Removal of the existing vent systems must be considered in the overall work scheduling since returning to power without a vent system would take long, be more difficult and increase personnel exposure. The construction must, therefore, be scheduled into a refuelirs outage of sufficient length to accommodate removal, installation, and testing.
Final system design and construction drawings have recently been received from the system vendor. However, based on a final detailed field review, some changes must be made to the layout for each unit to ensure access and operability of all components. In addition, material availability by the fall 1981 refueling outage for Unit 1 is uncertain and, thus, it is doubtful that the system installation will be completed durir.g 1981. Installation of the gas vent systems should be able to be completed on Unit 2 by June 1, 1982 and on Unit 1 by December 1, 1982, the next scheduled refueling outages.
Full operability of the systems will be based on the installation schedule of the ASIP panels.
Use of the gas vent system is addressed as part of the accident response procedures referenced in I.C.l. These procedures will be completed and available for training and operational review by March 1, 1982.
II.B.2.2 PLANT SHIELDING The initial post TMI-2 shielding and plant access calculations for Point
, Beach were performed using the source terms specified in NUREG-0578 (Reference 1).
The clarification in NUREG 0737 changed the assumptions used to develop the source terms and this impact was preliminarily evaluated by the sam- consultant that performed the initial calculations. Based on the results of this evaluation with regard to plant changes, it ha: been recommended that a complete re-evaluation be done. This evaluation would affect the implementation of the shielding
.odifications being evaluated for the Point Beach Nuclear Plant in three areas of the auxiliary building. Installation of permanent shielding, relocation of plant equipment, or the use of temporary portable shielding to reduce post-accident exposure of equipment and personnel is being considered. Each of these is described below.
A consultant, has Lequn the basic design evaluations for relocation of portions of the Unit 1 safety injection lines. This relocation could eliminate the major radiological contributor to exposure of adjacent electric.a1 equiment and reduce the dose rates for personnel access in the corridor beneath the existing piping. Since these modifications require the unit to be at cold shutdown and the purchase of safety-crade equipment, not yet designed, implemen-tation by the fall refueling outage in 1982 would be the earliest achievable date. Although work has begun on this modification, we do not believe that it is in the best interest of safety to make a change in an operating plant to a basic safety system which alters the initial design. The conditions
Revision 2 9/14/81 which are requiring such a change should be recognized to be a subset of conditions of an extremely low probability accident; an assumed unrealistic, worst case source term; and further, a postulated failure of normally highly reliable equipment. These conditions may not be consistent or logical but simply produce the worst case combination of factors.
A complete access study was performed with the existing piping configuration (Reference 1) and post-accident operations can be performed by minimizing access times. No equipment should fail due to radiation exposure within thirty days following the postulated accident (Reference 2). Based on the above and a parallel effort to satisfy the evaluation, documentation, and reporting requirements of IE Bulletin 79-OlB, " Environmental Qualification of Safety-Related Electrical Equipment", it is Wisconsin Electric's position that further effort on this change should be postponed until all other alternatives are considered.
Shielding for electrical equipment near a portion of the Unit 2 safety injection lines is under evaluation. Installation of any required modifications may be possible by the September 1, 1982 implementation date. No change in the safety injection line in this area is possible which does not increase the access and equipment concerns. The option of equipment evaluation is discussed in II.B.2.3 below.
Proposals for the evaluation and design of portable and permanent shielding in the current of the C-59 control panel (References 1 and 2) are currently being evaluated. Installation will not be possible by the January 1,1982 NRC implementation date. It is anticipated that portable shielding can be ordered soon and may be available by April 1, 1982. The permanent shielding changes must be designed to be structurally compatible with the existing structure and this requires a longer lead time. It is estimated that construction could begin in spring 1982 coincident with other structural changes scheduled in that area of the auxiliary building. Projected completion of this work is September 1, 1982.
Additionally, wall penetrations for piping and electrical runs between the auxiliary and control buildings were identified as requiring shielding. This was made necessary by implementation of IE Bulletin 80-11, which required the removal of concrete block which filled the unused portions of these wall
- openings. New shielding for these penetrations has been designed for installation.
This work has begun and is scheduled for completion prior to the June 30, 1982 NRC implementation date.
We are aware of the present differences between t.egments of tha scientific and nuclear industry communities and the NRC concerning source terms specified.
To the extent that these differences remain unsolved and change, the final implementation of any modifications may be altered.
! II.B.2.3 PLANT SHIELDING - EQUIPMENT QUALIFICATION Motor controls centers 1B32 and 2832 which are subject to the postulated radiation sources from the Unit 1 and Unit 2 safety injection lines, respectively, are being added to the electrical equipment considered under IE Bulletin 79-01B. This equipment is, therefore, being considered on the same schedule w - - - - - - w - , - - 4 am , w -
e v
t R visien 2 9/14/81 and under the same requirements as the other IE Bulletin 79-01B electrical equipment. Any modifications to be performed to meet II.B.2.2 will follow
- the completion of this evaluation.
II.B.4 TRAINING FOR MITIGATING CORE DAMAGE l
2 NUREG-0737 established the current requirements for training fc" mitigating core damage. The primary requirements are that the program be developed by
. January 1,1981, and that training be completed by October 1,1981.
- Development of a detailed Point Beach training course "o mitigating core i
damage was originally delayed because it was unclear exactly at what depth the program should be taught, lack of pertinent technical information, and
! because qualified manpower was unavailable in the Point Beach training group that could be diverted from attending to the other train'ng requirements resulting from TMI-2. Those other training requirements include Shift Technical Advisor training, additional simulator training, and augmented licensed operator training to meet new and increasing NRC requirements.
It was anticipated that material from vendor courses would become available which could be adapted to Point Beach. It was also anticipated that addi-tional qualified training personnel could be made available to prepare the program. Prior to 1981 only a limited amount of vendor material was available 4
and, therefore, the January 1,1981 deadline could not be met. Also, because
{ of the concurrent demands placed on all levels of nuclear plant personnel, it has been difficult to even retain experienced personnel and impossible to 1
increase manpower available for training, except at the expense of other areas.
As an alternative, we then issued a purchase order for our nuclear steam supply system vendor to provide a program specific to Point Beach. The NSSS vendor program was not ready until after March 1981; consequently, we were
- not able to meet the April 1, 1981 deadline either. The program description and content was provided on March 31, 1981 (Reference 22) as an attachment entitled, " Point Beach Nuclear Plant, Mitigating Core Damage Training Program",
Revision 0, March 16, 1981. Table 1 of that attachment provided the specific training requirements for plant personnel.
Part 1 training for this program was integrated into and completed as part of the licensed operatcr retraining program. All licensed plant personnel and
- Duty Technical Advisors completed this training prior to March 31, 1981. The remainder of the training program began on August 30, 1981. Completion of training for all individuals involved is scheduled for completion by October 1, 1981.
- 11. D.1. 2 PERFORMANCE TESTING OF BWR AND PWR RELIEF AND SAFETY VALVES (NUREG-0578, SECTION 2.1.2)
As the NRC is aware, the program (Reference 10a) has been expanded to include additional testing as explained in Mr. R. C. Youngdahl's July 24, 1981 letter -
to Mr. H. R. Denton entitled " Status of EPRI PWR Safety and Relief Valve Test Program, NUREG-0737, Item II.D.1" (Reference 39). Because of this additional
Revision 2 9/14/81 testing, the schedule for completion of the test reports and plant-specific analysis has been revised as identified in Mr. Youngdahl's letter. '
Since the Wisconsin Electric effort for Point Beach Nuclear Plant is dependent '
upon the overall test program, it is necessary to revise the schedule contained l in Reference 23 as follows: 1
, a. Complete Testing - June 30, 1981
- b. Plant-Specific Report - Three months after piping data from the testing program is available for use. A tentative date of May 1, 1982 is projected.
The Point Beach Nuclear Plant utilizes Crosby safety relief valves (HB-BP-86, 4-K2-6) and Copes-Vulcan power-operated rel!ef valves (D-100 with 2-h operator and 17-4 ph plug and cage) on both nuclear ureits. While a directly comparable Copes-Vulcan PORV is included in the test program, the test results for different Crosby safety relief valves (interpolation between a 3K6 and a 6M6) will be the basis for demonstrating acceptable valve performance.
The Copes-Vulcan PORV was tested at the Wyle facility in late July 1981. For all tests, the valve opened and closed on demand. After disassembly, no damage was observed that would affect valve performance.
A Crosby 3K6 valve was been subjected to a series of tests in late July and August at the Combustion Engineering .%cility. While the preliminary data indicates that for some tests the EPRI screening criteria were not met, the '
valve did open and relieve pressure; some valve " chattering" was observed.
Testing of a Crosby 6M6 valve had not been initiated as of August 31, 1981.
II.D.1.3 RELIEF ANIf SAFETY VALVE TESTING REQUIREMENTS - BLOCK VALVE TESTING A small number of block valves are part of the EPRI testing program test configuration. While the operability of block valves is not a safety issue, i the testing performed by EPRI at the Marshal Facility will be documented.
! Block valve results that come out of the PORV test program wil! thsrefore be utilized, but it is not our intention to do any block valve testing beyond that program. Point Beach Nuclear Plant has been analyzed for a spectrum of break sizes that bound the size of a stuck-open PORV and block valve. The analysis shows the Plant to be safe for this pastulated event.
I II.D.3.1 DIRECT INDICATION OF RELIEF AND SAFETY VALVE POSITION j Adapters and lift indicating switch assemblies will be mounted on the pressurizer i safety valves to provide direct indication of valve position. The assemblies j will be purchased from Crosby for use on Crosby valves. These switch assemblies l use magnetically operated reed switches to provide separately pcwered redundant open, midpoint and closed indications. These indications will be located in the control room.
l _ ,- _ _ ___ . _ _. ._. _ __ _ _ . _ _ -_ _ . _ , ,
Revision 2
. 9/14/81 The lift indicating switch assemblies are not presently qualified but Crosby is expected to qualify the assemblies in the future. The reason the lift indicating switch assemblies will be installed is that they are easier to environmentally qualify than the presently installed acoustic monitoring system. The presently installed acoustic monitoring system will continue to be used until the new assemblies are installed.
Installation of the lift indicating switch assemblies is presently planned for the spring 1982 refueling of Unit 2 and the fall 1982 refueling of Unit 1.
II.E.1.1 AUXILIARY FEEDWATER SYSTEM EVALUATION Over the past several years, the NRC has requested information regarding the design, instrumentation and operation of the auxiliary feedwater (AFW) systems for the Point Beach Nuclear Plant, Units 1 and 2 (References 1, 2, 3, 4a, 12, and 24). Wisconsin Electric has responded to these requests and provided the necessary information to satisfy each point raised. The only remaining item to be addressed is that of automatic protection of the AFW pumps if the AFW system water supplies are not completely protected from damage following a seismic event or tornado.
Wisconsin Electric continues to maintain the position that the condensate storage tanks, although not Class I water sources, are reliable and designed to specific, adequate seismic criteria. In the absence of NRC acceptance of this as sufficient, we have subsequently agreed to study the feasibility and desirability of providing pump protection through automatic AFW pump trips on low suction pressure as an alternative to automatic switchover, which would decrease rather than increase system reliability.
Wisconsin Electric has reluctantly decided to implement the automatic AFW pump trips as part of the instrumentation effort in progress. We have completed the basic design of the AFW suction pressure instrumentation channels. The procurement of safety grade, environmentally qualified equipment is in progress and installation will be integrated with the other instruments, equipment and cable routing. Implementation will require the Foxboro Spec 200 racks for both units to be instc led and operational, which is scheduled for early 1982. The design of the modifications to be made to the AFW pump control circuitry has not yet begun. A complete and thorough review of any design will ensure that no decrease in the reliability or operability of the AFW system results from these changes. A schedule for this work has yet to be determined.
II.E.1.2 AdXILIARY FEEDWATER SYSTEM INITIATION AND FLOW - FLOW INDICATION The auxiliary feedwater system indication of flow to each steam generator was implemented for Unit i during the fall 1980 refueling outage. The Unit 2 steam generator flow indication was implemented during the spring 1982 outage.
A single channel is shown schematically in Figure II.E.1.2. Auxiliary feedwater pump discharge flow is also monitored and indicated on the control board for operator use.
Revision 2 9/14/81 The auxiliary feedwater system and flow isdication has been described in References 1, 2, 3, 9, 12, 23, 24 and submittals by Wisconsin Electric in response to IE Bulletin 79-06B.
The steam generator flow indication instrumentation channels implemented are being environmentally qualified to meet the requirements of IE Bulletin 79-018. The model of Foxboro transmitter used in the 3ystem is currently undergoing a complete 79-018 environmental testing grogram. This program is scheduled for completion by June 30, 1982. Any changes required of the installed transmitts - sill follow the program completion.
Ultimately, power to the flow indication instrumentation channels will originate from highly reliable, battery-backed, Class IE power sources. Implementation of this power source will, however, require the completion of an instrument bus upgrade involving new chargers, batteries, inverters, and electrical distribution equipment. The design of this modification is nearly complete.
Construction and installation will be completed consistent with other TMI modifications, with cperation expected by July 31, 1982. Until then, the channels will be powered by diverse, highly reliable, non-battery-backed power sources. Full implementaticn of this modification is dependent upon new controls located on the ASIP.
Periodic testability has been designed into the channel circuitry. Channel component purchase, handling, and installation was covered under the Quality Assurance program implemented at Point Beach. Display of auxiliary feedwater flow to each steam generator is continuous and was installed taking into consideration operator use, control room human engineering, and available space on existing control boards.
II.E.4.2.1/4 CONTAINMENT ISOLATION DEPENDABILITY - IMPROVED DIVERSE ISOLATION ,
As originally designed, Point Beach met the NRC criteria for diversity of isolation and manual, single valve restoration (Reference 3: NUREG-0578, Item 2.1.4, LL Cat. A). Two out of three areas of NRC concern have been previously completed. These were revisions to administrative and ope.ating procedures and modification to the remote control switch for outboard purge valve CV-3212 (Reference 2).
The remaining item is the addition of isolation valves inside containment to piping for letdown, seal water return, and steam generator blowdown. Note redundant, diversely actuated isolation outside of ccntainment already exists.
Auxiliary charging has been removed from this list since it already has inside isolation and the normally closed manual valve outside will be locked closed or administratively controlled if opened. The blowdown valves were added to this list due to the location outside of containment of the existing isolation valves in an arca which might possibly be subject to falling debris from a block wall.
The addition of inside containment isolation valves on the letdown, seal water return, and steam generator blowdown lines is in the process of being implemented utilizing the services of an outside consultant for the piping and support design and analysis.
- RIvision 2 9/14/81 The remote air-operated isolation valves have been ordered from Copes-Vulcan.
The delivery schedule for the valves is 48 weeks and, thus, installation could take place during the fall 1?92 refueling outage for Unit 1 and the spring 1983 refueling outage for Unit 2 with completion by June 1, 1983.
Yet to be purchased, however, are the manual isolation, vent, and drain valves required to test the auto-isolation valves. Of the nine vendors who were asked to bid on supplying these valves, only two have responded. The shorter delivery time is 26 weeks while the longer is 46 to 60 weeks. We intend to purchase Anchor / Darling valves per the 26-week schedule provided the vendor has acceptable QA and certification / documentation programs. This should not delay the installation of the isolation valves.
II.F.1.1/2 ACCIDENT MONITORING - NOBLE GAS, IODINE, AND PARTICULATE Wisconsin Electric is currently in the process of upgrading the entire radiation monitoring system for the Point Beach Nuclear Plant. Wisconsin Electric has purchased an Eberline radiation monitoring system and anticipates that it will be installed and operational by April 1, 1982. Accident monitoring for effluents has been integrated into the upgraded system. The effluent monitoring equipment which was purchased from Eberline consists of three model SPING-4 I monitors, one model SPING-3 monitor and four model SA-11 monitors. The SPING monitors will be used for monitoring exhaust stacks and the SA-ll monitors will be used to monitor steam releases. It was originally envisioned that the SPING monitors would satisfy the exhaust stack sampling and monitoring criteria. However, due to changes issued in the NRC clarifications, the SPING monitors will not satisfy the particulate and iodine sampling criteria of II.F.1.2. They will, however, still provide the full range of nobla gas monitoring required. In view of this, a separate sampling system (referred to as the Isokinetic Stack Sampling System [ISSS]) is being purchased from another vendor and will be integrated into the upgraded system. An overall system description is provided. The details of each of tne above effluent monitors (SPING, SA-11 and ISSS) follows the overall system description .
System Description
The upgraded radiation monitoring system is a microprocessor-b ised radiation detection system. The heart of the system is eight Data Acqui;ition Modules (DAM) and four SPING monitors. Each SPING has a DAM built int it. Each DAM has a microcomputer which performs the tasks of data acquisition, history file management, operational status check, and alarm determination. Each DAM is capable of serving nine detector inputs and six analog inputs. The operator interface with the system is through a Control Terminal (CT-2) and a color graphics minicomputer (CRT-1). A functional block diagram of the system is shown in the attachment.
System Operation Radiation is detected and the signals processed by the electronics in a component called an interface box. The output signals from the interface boxes are input to the microcomputer. These signals are converted to count rate by the microcomputer which then parforms all mathematical calculations and control functions. The mathematical calculations include the application
i Rsvisien 2 9/14/81 of conversion factors and background subtraction. Each microcomputer maintains a history file for each of its input channels. The history '#1e consists of the last four hours of ten-minute averages, the last twenty-four hours of one-hour averages and the last twenty-four days of one-day averages. Each DAM (and SPING) nas a local readout panel. The local readout device is capable of accessing the current status of any channel associated with that particular DAM. The DAM's are connected to two CT-2's. Each CT-2 drives a CRT-1. Each CT-2 has its own keyboard, printer and system status annunciator.
The annunciator consists of an audible alarm and status lights. Each CT-2 includes a microcomputer which performs the functions of polling each DAM for operational status and data, logging any changes in status and associated data, logging history files automatically, performing calculations on history file data and annunciating alarm conditions and communication error messages.
The CRT-1 operates independently of the CT-2 and has access to all of the CT-2 f.. formation. The Cr?-l ccnstantly displays all channels which are in alarm and gives the op. %or the capability of graphically trending any channel. In addition, each DAM can be locally interrogated for current status and history files by a portable terminal. The Point Beach control room will be equipped with one CT-2 and one CRT-1. The Point Beach Technical Support Center will be equipped with either a CT-2 or CRT-1, but not both.
The entire upgraded radiation monitoring system will be powered from the vital (instrument) busses. The instrument bus provides power to each DAM.
The DAM provides the power to each of its associated channels. In addition, each DAM is equipped with a battery which provides for eight hours of continuous operation in the event of a power failure.
A. SPING Monitor The Eberline SPING monitor is a self-contained microprocessor-based radiation detection system used to sample and monitor particulates, iodine and noble gases in the air. The sample intake (refer to attached figure) goes through a filter paper on which particulates are deposited, then through a charcoal cartridge to trap iodines and then into the gas chamber for low and medium range noble gas measurement. The sampla then passes through a high-range noble gas chamber, through the pump and to the sample outlet. The SPING-3 is the only SPING which is not equipped with a high-range noble gas chamber. The high-range noble gas chamber is the only differentiator between a SPING-3 and a SPING-4.
The upper counting 6 range of the particulate, iodine, and low-range noble gas channels is 10 cpm. The beta particulate channel is approximately 12% (4n) efficient for Cs-137 beta particules. The I-131 gamma scintil-lation channel is approximately 4% (4n) efficient for the 364 kev gamma from I-131 7decay. Tgelow-rangenoblegaschannel'suseablerangeis from 1x10 to 4x10 pCi/ccfgrXe-1333 The medium-range noble gas channels range is from 2.5x10 to 1x10 pCi/gcforXeg133. The high-range gross gamma channel has a range of 1x10 to 1x10 pCi/cc for Xe-133.
An area monitor measures ambient radiation levels and has a range of 1 pR/hr to 100 mr/hr.
The SPING features stainless steel plumbing through the sampler stages, a photohelic flow indicator with low and high flow setpoints, remote flush valves, a manual grab sample port with nose barbs, a sealed diaphram air pump and a connection plug for a portable terminal.
1
I '
R:visicn 2
. 9/14/81
- 1. Instrumentation
- a. The particulate filter is monitored by a beta scintillation detector from one side (Eberline model RDA-3A) and a solid-state alpha detector on the other side (Eberline model RDS-1).
Counts from the beta detector are a measure of the amount of beta emittina isotopes on the filter. The alpha detector measures th- "adon levels in the sample to provide a measure of the contribution of these daughter products to the beta
- particulate levels. This contribution can then be corrected by subtracting a factored amount of the alpha measurement from ,
the beta measurement. This technique is used to compensate l for the effects of fluctuating radon / thoron levels in the beta particulate measurement.
- b. The charcoal cartridge is monitored by a 2" x 2" NaI gamma scintillation detector. This detector (Eberline model RDA-2A) is gain stabilized to minimize the effects of drif aused by fluctuations in temperature and/or aging. The mea.. ement is accomplished using a single channel analyzer (SCA) with its window calibrated to the 364 kev energy of I-131. .There is an additional SCA with its window calibrated to an energy above the I-131 energy to provide a measure of the background in the iodine window. The effects of a fluctuating background are compensated for, by subtracting the background.
- c. The low-range noble gas monitor is a beta scintillation detector (Eberline model RDA-3A). Background correction for this
! channel is derived from the gamma background detector which is '
! an energy compensated Geiger-Mueller (G-M) detector (Eberline model 10450-B28). Since the external (ambient) gamma radiation
- has a measurable effect on the beta measurement (particulate and gas), the gamma background channel is used as a source of subtraction for both the gas measurement and the particulate i
measurement.
i
, d. An energy compensated G-M detector (Eberline model 10450-828) l monitors the gas volume for-the medium-range noble gas measurement. ;
Its output is proportional to the gamma emission of the sample.
An additional identical detecter, the background detector, is provided in the sampler shield as a measure of external background at the sampler. Tius, the effect of a fluctuating external background on the medium-range gas channel are nullified by measuring and subtracting the background.
$ e. An energy compensated G-h detector (Eberline model 10450-828) i monitors the cas voluta of a section of 1" stainless steel.
- tubing in the 5A-9 high-range noble gas sampler of the SPING-4.
Its output is proportional to t%a gamma emission of the sample.
- f. Each SPING is equipped with a local area monitor. This detector is an energy compensated G-M tube (Eberline model DAI-1-CC) which is calibrated in radiation dose rate and provides a measure of the gamma field at the instrument.
L
I Revisicn 2 9/14/81
- g. Radioactive check sources are provided to enable periodic checking of the detectors and electronics for proper response.
The following list summarizes the channels with check sources.
CHANNEL CHECK SOURCE Beta Particulate 30 pCi Cs-137 Iodine 0.5 pCi Ba-133 Low-Range Noble Gas 30 pCi C5-137 Area Monitor 0.5 pCi Sr-90, Y-90 High-Range Noble Gas 0.5 pCi Sr-90, Y-90
- h. A complete list of detector specifications, sampler speci-fications and calibration procedures is included in the attachment.
- 2. The SPING-4 monitors will be used to monitor the exhaust flow of the Unit 1 containment purge exhaui.t stack, Unit 2 containment purge exhaust stack and the auxiliary building exhaust stack. These monitors will be located in the electrical equipment rooms. The sample connect point for these monitors will be downstream of the stack filters. The SPING-3 monitor will be used to monitor the exhaust flow of the Point Beach radwaste packaging area exhaust stack. The SPING-3 will be located in the radwaste packaging area.
The sample connect point for the SPING-3 will be located downstream of the filters. ANSI N13.1-1969 will be used as the guidelines for the design of nozzles and piping layout.
B. SA-11 Monitor The upgraded radiation monitoring system includes four SA-11 monitors for steam line monitoring. The SA-11 is comprised of a lead-shielded detector which views the main steam line upstream of the safety valves for gamma radiation. A typical location diagram is shown in the attachment. The detector is an energy compensated G-M tube (Eberline model 10450-B28).
The detector output is proportional to the gamma emission from the steam line. The detector cutput is input to a single channel on a DAM. The SA-11monitorisequippedwitharemotelyactuatedghecksougce(0.5pCi Sr-90, Y-90). The range of the SA-ll is from 1x10 to 1x10 mR/hr. The exact conversion to pCi/cc of Xc-133 he not yet been determined. The calibration procedure for this monitor is expected to yield the appropriate conversion factors. The calibration procedure is currently being developed.
The monitor and detector specifications are included in the attachment.
C. Isokinetic Stack Sampling System (ISSS)
The ISSS is being designed to satisfy the requirements of II.F.1.2.
However, due to the untimely response of vendars to the Wisconsin Electric request for proposal, exact design details cannot be presented at this time. The conceptual design and specifications will be presented. It is anticipated that this system will be installed and operational by May 1, 1982. This system will be installed on the auxiliary building exhaust stack and the radwaste packaging area exhaust stack since they are the only viable early celease paths in an accident situation.
R2visicn 2 9/14/81 A functional block diagram of the ISSS is shown in the attachment. A representative sample will be drawn at an isokinetic rate with respect to stack flow. The unit will maintain isokinetic sampling capability up to the design flow of 62,000 cfm with an error of less than +20%. The system will be capable of continuous operation. The stack flow sensor and sample flow monitor will be high quality devices. The flow controller will be capable of both automatic and manual operation. The stack flow transmitter will provide a 4-20 ma signal for input to the DAM analog input boards. The Flow Control Valve (FCV) will be of high quality.
System temperature control will be provided. Local indicators for stack velocity and flow and sample velocity and flow will be provided. The length of the line between the sample withdrawal and the sample collector will be as short as possible. The collector must be shielded. Quick changeout of the collection media is required to minimize personnel exposure.
All vendors were advised that particulates and radioiodines were the species to be collected. Vendors were directed to prooose a collector which meets the requirements of NUREG-0737. Vendors were supplied with a list of references which included NUREG-0737, ANSI N13.1 and Regulatory Guide 1.97, Revision 2.
D. Procedures for Relaase Rate Calculations Copies of the current procedures and calculational methods for quantifying releases are in the attachment. These procedures are part of the Point Beach Emergency Plan Implementing Procedures. These procedures will be updated as required in order to reflect the upgraded radiation monitoring system.
II.F.1.3 ACCIDENT MONITORING - CONTAINMENT HIGH-RANGE RADIATION MONITOR Additional in-containment high-range radiation monitoring will be provided for Point Beach Nuclear Plant by six gamma ionization chambers supplied by General Atomic Company. Three RD-23 detectors with an eight decade range will be located on floor- or beam-mounted seismic supports located on the 66' El. operating level in each unit's containment. Power for each detector and signal processing will be provided by RP-2C readout modules mounted in new auxiliary instrumentation racks located in the computer room above the control room. Each deft: tor will be supplied power from a separate safety grade instrument bus via an individual power supply associated with the RP-2C readout module. Power for each bus originates with a battery / charger-supplied inverter to ensure continuous operation. Separation and seismic support provide IE qualification for the detector channels.
The output of the individual detector channel will be processed by Foxboro Spec 200 instrumentation to be installed in the same area. The outputs will be isolated and routed to the ASIP for display and high-level alarm annunciation.
Additional outputs will be provided for the plant computer and instrumentetion systems.
Installation of the in-containment monitors can be accomplished during the next refueling outage for each unit, fall 1981 for Unit 1, and spring 1982
R:visicn 2
. 9/14/81 I
for Unit 2, provided the supports are received in time. Operation of the l entire system is dependent upon delivery and installation of the ASIP ,
(September 1982), Foxboro racks (late 1981 and early 1982 for Unit 1 and 2, I respectively) and the auxiliary racks (not yet ordered).
II.F.1.4 CONTAINMENT PRESSURE MONITOR New high-range pressure transmitters will be installed to provide containment wide-range pressure indication. Indication and recording will be provided in the control room.
This indication system is typical of many that are being installed. It consists of several components, each with their own schedule, as follows: ;
1
- 1. Foxboro pressure transmitters have been delivered and are on-site.
Transmitter mounts meeting seismic design criteria and Quality Assurance standards must be fabricated. It is expected that these transmitter mounts will be fabricated and the transmitters mounted by the end of 1981, for both Unit 1 and Unit 2.
- 2. Foxboro Spec 200 analog process racks have been ordered. These racks will power the transmitters and process and isolate the transmitter output signals. Delivery of the Unit I racks is expected near the end of 1981 and delivery of the Unit 2 racks is expected early in 1982.
- 3. Interconnecting cables must be pulled and terminated. These cables connect the transmitters to the Foxboro racks, the racks to the main control board in the control room, the racks to the Auxiliary Safety Instrumentation Panel (ASIP) in the control room, and the racks to the computer system. These cables will be installed during 1981 and 1982 as equipment is installed.
- 4. Power for the white and yellow powered Foxboro Spec 200 racks will be supplied by new battery-inverter power supplies. The batteries will be located in new battery rooms which will be constructed. It is estimated
( that the new power supplies will be available June 30, 1982.
- 5. Readouts in the control room will be mounted on the existing main control board (panel C01) and the new ASIPs (panels 1C20 and 2C20). The C20 panels will be ordered and it is expected that they can be designed, fabricated, and delivered by June 30, 1982.
Although portions of the high-range containment pressure indicating system may be operating sooner on an interim basis, it is currently expected that the final configuration of the analog indications in the control room will be
, operational during September of 1982. The same constraints that apply to the l high range containment pressura system also apply to most of the other indication systems that require display in the control room.
l
! 1 l
[
Revision 2 L i
. 9/14/81 J
II.F.1.5 CONTAINMENT WATER LEVEL ;
DeLaval-Gems tra7smitters and receivers have been delivered and are on-site.
1 The Unit 1 transmitters will be installed during the fall 1982 refueling if '
j seismically designed transmitter mounts can be fabricated with the proper Quality Assurance provisions in time for installation this refueling. It is planned to install the Unit 2 transmitters during the spring 1982 refueling.
The receivere will be wall mounted in the computer room. Installation of the
! receivers is expected during the latter part of 1981.
l The Foxboro Spec 200 racks will be used to distribute the receiver outputs to the computer and to the ASIP. The constraints and implementation schedule i mentioned in II.F.1.4 with respect to the racks, cables, power supplies, and ASIP also apply to the containment water level indications.
II.F.1.6 CONTAINMENT ATMOSPHERE HYDROGEN ANALYZER i
Redundant hydrogen sensors powered by independent power supplies will be provided in each containment. The analyzers that will be ordered are manu-
- factured by Exo Sensors, Inc. The ordt- has not been placed as yet pending the outcome of Exo Sensor's qualificat,on test program which is in progress.
It is planned to mount the sensors in the Unit 2 containment during the 4 spriag 1982 refueling and to mount the sensors in the Unit 1 containment durirg the fall 1982 refueling. Cable runs are expected to be installed in the Unit 1 containment during the fall 1981 refueling. Cables have already
- been installed in the Unit 2 containment.
I The microprocessors will be installed in auxiliary racks in the computer rcom. These auxiliary racks have not been ordered as yet, i
- The Foxboro Spec 200 racks will be used to distribute the analyzer outputs to the computer and to the ASIP. The constraints mentioned in II.F.1.4 with respect to racks, cables, power supplies and the ASIP also apply to the
! containment atmosphere hydrogen analyzer indications. It is expected that ,
j the system from sensors to indicators in the control room can be operational for both units by December of 1982.
1 II.F.2.1 INSTRUMENTATION FOR DETECTION OF INADEQUATE CORE COOLING -
SUBC00 LING METER The final subcooling system which will meet all of the NRC requirements has been designed as part of the qualified instrumentation system being added to ;
l the plant. This added system is intended to provide the means by which the '
large number of instrumentation changes can be properly incorporated into the
. existing plant. This new system consists of five insttuments and an ASIP for
! each unit. The ASIP is located in the control room at a location which l allows for easy viewing of the panel-mounted display devices. Subcooling '
display meters will be located on the ASIP. The operability of the final subcooling meter is dependent upon the delivery, installation and operational checkout of the new racks and panels. The new panels are each fifteen feet I l l
l _. _ _ _ _ _._. _ _ ___ __ _ _ _ . _ _ _ _ _ _ . _ _ _
R:visicn 2 9/14/81 long and their installation in the control room must be carefully planned and implemented. The ordering of these panels has been delayed due to the continuing need to add instrumentation to them and route cable and conduit through them as new requirements are recognized. The design ~of these panels is close to being finalized and the procurement of these panels is about to begin. It is our plan to have the ASIP panels delivered in June of 1982 and the displays located on these panels should be operational by September of 1982. This includes the final configuration of the subcooling display. The subcooling capability described in References 1 and 2 is judged to be sufficient until the final system is operational in the Plant.
II.F.2.3 REACTOR VESSEL WATER LEVEL The reactor vessel water level system uses redundant, separately powered wide- and narrow-range Foxboro differential pressure transmitters located inside containment, four transmitters per unit. These transmitters have been delivered and are on-site. Installation of the Unit 1 transmitters will be performed during the fall 1981 refueling outage 4f seismically designed transmitter mounts can be fabricated with the proper Quality Assurance provi-sions in time for installation this refueling. It is planned to install the Unit 2 transmitters during the spring 1982 refueling.
The top fluid connection to the reactor vessel head will be made by Westinghouse Electric Corporation. It is planned that this connection will be installed in Unit 1 during the fall 1981 refueling and in Unit 2 during the spring 1982 refueling.
The bottom fluid connection to an incore instrumentation thimble guide tube coupling will be made by NUS Corporation. It is planned that this connection will be installed in Unit 1 during the fall 1981 refueling and in Unit 2 during the spring 1982 refueling.
t At the high point of the top tap fluid lines, a chamber will be installed l with sufficient capacity to refill the fluid lines to the transmitters once.
This chamber acts as a water reservoir; it does not contain a bellows or diaphram. The chamber, its supports, and supports for the fluid lines will be seimically designed and fabricated with the proper Quality Assurance l provisions. It is expected that these elements of the system will be installed I
in Unit 2 during the spring 1982 refueling outage and in Unit 1 during the fall 1982 refueling outage.
Chromel-alumel thermocouples will be attached to the vertical runs of the fluid lines to provide temperature compensation. It is expected that these i
thermocouples will be installed in Unit 2 during the spring 1982 refueling and in Unit 1 during the fall 1982 refueling.
' The reactor vessel incore thermocouples and the thermocouples on the vertical runs of the fluid lines will be processed by input cards in the new computer multiplexing system. The computer multiplexing system will output weighted-average signals to the Foxboro racks. It is expected that the computer multiplexing system will be installed by November 1982.
i
R; vision 2
' 9/14/81 The top tap fluid line is being designed to penetrate through the refueling canal wall in order to maintain proper elevations. This fluid penetration thrcugh the refueling canal wall will be fabricated and a hole will be drilled through tie wall to accept the penetrution. It is expected that this penetration will be installed in Unit 2 during the spring 1982 refueling and in the Unit 1 during the fall 1982 refueling.
Foxboro Spec 200 analog process racks will be used to power the differential pressure transmitters, perform the computations, and distribute the output signals to the computer and ASIP. The constraints mentioned in II.F.1.4 with respect to the racks, cables, power supplies and ASIP also apply to the reactor water level system. It is expected that the system from sensors to indicators in the control room can be operational for both units by December of 1982.
A detailed description of the vessel level system showing the tap locations, fluid line routing, transmitter location, signal processing and parameter displays will be submitted by October 1, 1981. The system utilizes vessel differential pressure to determine level but it is not a Westinghouse-designed or supplied system. The questions on the Westinghouse system sent to Wisconsin Electric by the NRC in Reference 41 will be addressed, where applicable, in our October 1, 1981 submittal.
II.K.3.5 AUTOMATIC TRIP OF REACTOR COOLANT PUMPS DURING LOSS-OF-COOLANT ACCIDENT The Owners Group of Westinghouse utilities submitted material in OG-60, R. W. Jurgensen to P. S. Check letter dated June 15, 1981 (Reference 31),
which documented post-test analysis of LOFT test L3-1 and L3-6. Reference 31 stated that the schedule to submit a proposed automatic RCP trip, if such a trip is determined to be necessary, will not be required until at least three months after the NRC has approved the small break model.
III.A.1.2 UPGRADING EMERGENCY SUPPORT FACILITIES The conceptual design information for the emergency response facilities at Point Beach was submitted to the NRC in letters dated February 18, 1981 (Reference 15a) and June 1, 1981 (Reference 28).
The instrumentation described in Reference 2 was installed in the temporary Technical Support Center prior to March 1,1981 and is fully operational with the following exceptions:
- 1. Wind speed and direction indicators cannot be installed on a temporary basis,
- 2. The remaininghT and cT f r Unit 2 will be installed by October 1, 1981,
- 3. Containment sump level, and
- 4. Containment high-range radiation.
Rrtision 2 9/14/81 Items 3 and 4 will be operational when the new instrumentation racks and ASIP's are installed and operational by September 1982. The value of connecting them to the temporary Technical Support Center (TSC) will be determined at that time.
When the new TSC is completed, the interim instrumentation system will be moved to the emergency operations work area. This move should occur by February 1, 1982, at which time the new TSC can be considered operational.
This system is judged to be adequate until the final computer-based plant data system is operational around September of 1983.
A training session was held on March 11, 1981 for all Duty and Call personnel and all Duty Technical Advisors to cover the parameters display. User instructions have been developed for the interim system and are located close to the display panel.
Clarification of various emergency response facilities items is as follows.
This item (III.A.1.2) is being considered to be applicable to the physical facilities of the TSC, OSC and E0F. The Emergency Plan is addressed in II.A.2.1, the meteorological data system is addressed in III.A.2.2, and the plant safety parameter display console is addressed in I.D.2. Since the technical data system is part of the same computer system as the SPDS, it will be considered in I.D.2.
III.A.2.1 EMERGENCY PREPAREDNESS - UPGRADED EMERGENCY PLANS TO APPENDIX E, 10 CFR 50 Copies of the revised PBNP Radiological Emergency Response Plan, as well as copies of the State and local plans, were submitted on December 30, 1980 (Reference 12b).
The PBNP Plan submitted was complete except for the fifteen-minute notifi-cation and Table B-1. In Reference 30, a public notification system was described for PBNP. Revisions of the local radiological emergency response plans will be made by the counties for inclusion in the State plan for submittal to the Federal Emergency Management Agency. A revision to the PBNP Emergency Plan will be made after the public notification system is operational. The functional requirements of Table B-1 were discussed in Reference 12b and an alternate Table B-2 was presented.
The Emergency Plan Implementing Procedures were submitted on February 27, 19C1 (Reference 17a), including a description of methods to assess and monitor potential off-site consequences of an emergency.
The upgraded Emergency Plan and its associated implementing procedures were implemented on March 31, 1981 in accordance with 10 CFR 50.4752.
Personnel at PBNP and the corporate headquarters that have a role in emergency response to an incident at PBNP have received training and hwe been entered into a retraining program on the Emergency Plan and applicable Emergency Plan Implementing Procedures.
R: vision 2
. 9/14/81 III.A.2.2 EMERGENCY PREPAREDNESS - METEOROLOGICAL DATA Wisconin Electric has provided in Reference 13 a description of its plans for upgrading the meteorological measurements program at Point Beach. Reference 38 stated that our submittal of a complete functional description of all elements of the upgraoed program discussed in Section G of Reference 13 will be provided prior to January 1,1982.
The meteorological measurements program is being design to interface with the computer system being installed to meet NUREG-0696 requirements (See Note I.D.2). This means of implementing the meteorological program will result in some delay in its implementation, but will result in an integrated system that is superior to any another means of implementation we were able to envision. The result is that Milestone 4 and Milestone 5 of Appendix 2 of
~
NUREG-0654 will not be completed by April 1, 1902 and July 1, 1982, respectively.
Projected completion dates will be provided prior to January 1,1982.
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, o e REFERENCES
- 1. S. Burstein (WE) letter to H. R. Denton (NRC), December 31, 1979,
" Implementation of NUREG-0578"
- 2. C. W. Fay (WE) letter to H. R. Denton (NRC), March 14, 1980, " Implementation of NUREG-0578"
- 3. A. Schwencer (NRC) letter to S. Burstein (WE), April 9,1980, " Evaluation of Compliance with Category "A" Lessons Learned Requirements" 3a. D. G. Eisenhut (liRC) letter To All Operating Reactor Licensees, May 7, 1980, "Five Additional TMI-2 Related Requirements (Applicable) to Operating Reactors"
- 4. C. W. Fay (WE) letter to H. R. Denton (NRC), June 11, 1980, " Implementation of Five Additional TMI-2 Related Requirements" 4a. C. W. Fay (WE) letter to H. R. Denton (NRC), June 11, 1980, " Additional Information Auxiliary Feedwater System"
- 5. C. W. Fay (WE) letter to H. R. Denton (NRC), November 3, 1980, " Status of Duty and Call Technical Advisor Training"
- 6. C. W. Fay (WE) letter to H. R. Denton (M."C), December 1, 1980, " Revised Emergency Plan"
- 7. C. W. Fay (WE) letter to H. R. Denton (NRC), November 3, 1980, " Operating Licenses DPR-24 and DPR-27, Interim Criteria for Shift Staffing"
- 8. C. W. Fay (WE) letter to H. R. Denton (NRC), September 22, 1980,
" Comments on Draft NUREG-0696, Functional Criteria for Emergency Rerponse Facilities"
- 9. S. Burstein (WE) letter to H. R. Denton (NRC), October 20, 1979,
" Implementation of NUREG-0578" - including TMI Accident Review Task Force Report (Section 3.6.A) 9a. P. F. Collins (NRC) letter to C. W. Fay (WE), October 28, 1980, regarding Item I.A.2.1.3 of NUREG-0737.
9b. R. F. Heishman (NRC) letter to Sol Burstein (WE), November 20, 1980, Inspection Report No. 50-266/80-19 and No. 50-301/a0-19.
- 10. R. W. Jurgensen (WGG) letter to S. H. Hanauer (NRC), 0G-47, December 15, 1980, " Westinghouse Owners Group Response to Item I.C.1 of NUREG-0737" 10a. R. C. Youngdahl (EPRI) letter to D. G. Eisenhut (NRC), December 15, 1980, PWR Utilities Position on NUREG-0737, Item II.D.1, Performance Testing of BWR and PWR Relief and Safety Valves (NUREG-0778, Section 2.1.2)
- 11. S. H. Hanauer (NRC) letter to R. A. Newton (WE), December 17, 1980, request for a basis document for the emergency procedure guidelines.
Revision 2
, . 9/14/81
- 12. C. W. Fay (WE) letter to H. R. Denton (NRC), December 23, 1980, " Response to NURG-0737, Schedule Requirements as Related to Point Beach Nuclear Plant, Units 1 and 2" 12a. R. F. Heishman (NRC) letter to Sol Burstein (WE), December 23, 1980, Inspection Report No. 50-266/80-20 and No. 50-301/80-20.
12b. C. W. Fay (WE) letter to H. R. Denton (Nk". December 30, 1981, " Point Beach Nuclear Plant Emergency Plan"
- 13. C. W. Fay (WE) letter to H. R. Denton (NRC), January 9, 1981, " Additional Response to NUREG-0737" 13a. C. W. Fay (WE) letter to H. R. Denton (NRC), January 19, 1981, " Response to NUREG-0737"
- 14. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), OG-48, January 28, 1981, " Emergency Operating Instruction Background Documents"
- 15. C. W. Fay (WE) letter to H. R. Denton (NRC), February 4, 1981, " Technical Specification Change Request No. 65" 15a. Sol Burstein (WE) letter to S. J. Chilk (NRC), February 18, 1981,
" Emergency Operatings Facility" 15b. D. G. Eisenhut (NRC) letter To All Licensees of Operating Plants and Holders of Construction Permits, February 18, 1981, " Post-TMI Requirements for the Emergency Operations Facility (Generic Letter 81-10)"
- 16. C. W. Fay (WE) letter to H. R. Denton (NRC), February 23, 1981, " Additional Responses to NUREG-0737"
- 17. C. W. Fay (WE) letter to H. R. Denten (NRC), February 26, 1981, " Duty and Call Technical Advisor Training" 17a. C. W. Fay (WE) letter to H. R. Denton (NRC), February 27, 1981, " Emergency Plan I,; kmenting Procedures"
- 18. C. W. Fay (WE) letter to H. R. Denton (NRC), March 4,1981, "NUREG-0737 Schedule Requirements"
- 19. R. W. Jurgensen (WOG) letter to J. R. Miller (NRC), 0G-52, March 13, 1981, WCAP-9804, "Probabilistic Analysis and Operational Data in l Response to Item II.K.3.2 for Westinghouse NSSS Plants"
- 20. R. W. Jurgensen (WOG) letter to S. H. Hanauer (NRC), 0G-54, March 18, 1981, " Westinghouse Owners Group Update on Item I.C.1 of NUREG-0737 Activities"
, 21. E. R. Mathews (WPS) letter to Sol Burstein (WE), March 19, 1981, l
" Letter of Intent to Provide Mutual Assistance" l
l l
l L
. - . = .-. . .. - ._. ..
Rsvision 2 9/14/81
- 22. C. W. Fay (WE) to H. R. Denton (NRC), March 31, 1981, " Emergency Plan"
- 23. C. W. Fay (WE) to H. R. Denton (NRC), March 31, 1981, " Response to NUREG-0737 Update to Schedule Requirements and Implementation Status"
- 24. C. W. Fay (WE) to H. R. Denton (NRC), April 9, 1981, " Requirements for Auxiliary Feedwater System"
', 25. C. W. Fay (WE) to H. R. Denton (NRC), April 14, 1981, " Post-TMI Requirements for the Emergency Operations Facility"
- 26. C. W. Fay (WE) to H. R. Denton (NRC), May 7, 1981, " Containment Pressure Setpoint, NUREG-0737 Item II.E.4.2" 26a. W. A. Wogsland (WOG) letter to L. Beltracchi (NRC), May 19, 1981,
" Proprietary Handouts, SAS Meeting, May 14, 1981"
Procedures Development and Evaluation Program"
- 28. Sol Burstein (WE) to H. R. Denton (NRC), June 1, 1981, " Emergency.
Response Facilities" 1
, 29. R. A. Clark (NRC) to Sol 8urstein (WE), June 1, 1981, " Clarification of Post-Accident Sampling Requirements of NUREG-0737, II.B.3"
- 30. C. W. Fay (WE) letter to H. R. Dentan (NRC), June 2, 1981, " Emergency Plan Public Notification System" -
, 1981, " Response to NRC Letter of May 30, 1981"
- 32. P. A. Clark (NRC) to Sol Burstein (WE), June 17, 1981, " Review of the t
Westinghouse Owners Group submittal for Action Plan Item I.C.1"
- 33. R. A. Clark (NRC) to Sol Burstein (WE), June 17, 1981, " Safety Evaluation by the Office of Nuclear Reactor Regulation (RE: IEB 79-06A nnd 79-06A, Revision 1, Item 7.I.K.1)
- 34. R. A. Clark (NRC) to Sol Burstein (WE), June 26, 1981, " Elimination of
) Item II.K.2.19"
- 35. C. W. Fay (WE) to H. R. Denton (NRC), July 6, 1981, "NUREG-0737 Schedule Update"
- 36. R. W. Jurgensen (WOG) to S. H. Hanauer (NRC), OG-61, July 7, 1981,
" Summary of WOG Program to Address NUREG-0737, Item I.C.1."
r
- 37. R. A. Clark (NRC) to Sol Burstein (WE), July 10, 1981, " Order Confirming Licensee Commitments on Post-TMI Related Issues" l 38. C. W. Fay (WE) latter to H. R. Denton (NRC), July 17, 1981, " Meteorological System Description" l
l l
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r Revision 2 1
, ; .- > 9/14/81 l
- 39. R. C. Youngdahl (EPRI) letter to H. R. Denton (NRC), July 24, 1981,
" Status of EPRI PWR Safety and Relief Valve Test Program, NUREG-0737, l Item II.D.1" l
- 40. R. A. Clark (NRC) to Sol Burstein (WE), July 28, 1981, " Request for Additional Information on Auxiliary Feedwater System"
- 41. R. A. Clark (NRC) letter to Sol Burstein (WE), August 5, 1981, " Westinghouse Reactor Vessel Level Instrumentation for Monitoring Inadequate Core Cooling"
- 42. R. A. Clark (NRC) to Sol Burstein (WE), August 14, 1981, " Containment Isolation Pressure Setpoint"
- 43. R. A. Clark (NRC) to Sol Burstein (WE), August 19, 1981, "TMI Task Plan Items II.K.3.9, II.K.3.10, and II.K.3.12 for Point Beach Nuclear Plant, Units 1 and 2"
- 44. C. W. Fay (WE) to Secretary of the Commission (NRC), August 25, 1981,
" Comments on NUREG-0739, Draft Criteria for Preparation of Emergency Operating Procedures"
- 45. Sol Burstein (WE) to H. R. Denton (NRC), August 28, 1981, " Technical Specification Change Request No. 68, Containment Purge Valve Operability" l
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. ATTACHMENT TO
, RESPONSE TO NUREG-0737' DATED SEPTEMBER 14, 1981 RADIATION MONITORING' SYSTEM POINT BEACH NUCLEAR PLANT- ..
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A RADIAT10ft M0filTORING SYSTEM FUNCTIONAL BLOCK DIAGRAM
+-- CT-2
> ,CT-2 --> CRT-1 CRT-1
(
Unit 1 Electrical Unit 2 Electrical Equipment Room Equipment Room DAM DAM DAM
_ DAM DAM DAM DAMP DAM
~
SPING-4 SPING-4 SPING-4 Radwaste Packaging Area
_ SPING-3 -
gi
- MODEL RDS-1 ,
- b. 3 inch lead shield - 9.75 pounds (4.43 kg).
A. GE.}ERAL DESCRIPTION
- The N!odel RDS.I is a combination filter holder C. TIIEORY QF OPERATION assembly and alpha detector. The detector is of solid .
. state design to provide energy resolution and is followed 1. GENERAL by an amplifier and a line driver. Addition of an IB-3R
, (analog readout system) or an IB.3C (digital readout Particles contained in the air stream are deposited system) provides the interface to the readout electronics. on the filter. Alpha radiation emitted by this particulate is detected, amplified, and transmitted to the interface When installed in a proper samp'er assembly, the box (IB-3).
-- RDS-1 provides a method of monitoring the particulate filter with both an alpha and beta detector that fur- Use of a solid state detector provides good energy
- nishes a dynamic measurement of radon. This measure- resolution for alpha radiation while showing little or no
'; ment can be subtracted from the beta channel. enhanc- sensitivity to gamma or beta radiation.
ing sensitivity and credibility of the beta measurement.
- 2. FUNCTIONAL THEORY
- B. SPECIFICATIONS
.a n. Detector
- 1. Detector: Silicon diffused junction type (cleanable) with 490 mm' area. .
When alpha particles bombard the detector, they enter the depletion region of the back biased-diode
- 2. Filter: 47 mm dia. hiillipote Shi or ejtuivalent junction. While these particles are in the depletion recommended. r'egion, they give up energy by causing ion pairs to be created."These ion pairs are created at the rate of one
. 3. Counting efficiency: Approximately 208'o of 2 pi ion pair per 3.23 eV of energy given up by the alpha
particle.
from a plated 47 mm dia. 2"Pu source in the filter holder.
Because of the high electric field, these ion pairs
- 4. Amplifier: Charge sensitive input allowing very are swept out, of the depletion region and the total high input sensitivity with excellent noise rejection. resulting charge is applied to the preamplifier input..
. Feedback provides stability and control. Gain is fixed i for approximately +0.IV output when exposed to a b. Amplifier 1 8"Pu source. ,
Transistors'Q1 and Q2 form a charge-sensitive t 5. Connector: Amphenol #165-34 (mating connector- preamplifier with an output proportional to the charge
- is on-!B-3). input from the detector. The feedba
- k capacitor C5
' c,'termines the sensitivity of this circuit. Constant cut-
- 6. Power requirement: ,24 VDC at 40 mA (provided tr source CRI sets QI bias current and, due to its high by IB.3). impedarice, provides a very high voltage pain from Ql.
Q2 is en emitter follower,that provides a low output im-
. 7. Temperature: Operational from 30' to 130'F (0'C pedance from the preamplifier.
to 55'C). Total gain change is less than 5%. ...
Transistors Q3 and Q4 provide gain and cable
- 8. Slechanical Sze: drive. Feedback for gain control is via R7/RTI and R3.
RTI compensates for the temperature characteristics of
- a. 2 inch lead - 7.12 inches (18.1 cm) long x 2.70 the detector.
inches (6.S5 cm) dia. oserall.
D. DISASSEN1BLY AND REASSEStBLY: (Refer to
- b. 3 inch lead - 8.12 inches (20.6 cm) long x 2.70 assembliprint)
- inches (6.S5 cm).dia. o>crall.
CAUTION Weight: -
If the detector face is scratched or if the detector '
- a. 2 inch lead shield - 7l4 pounds.(3.36 kg). ' receives too much shock, it can be permanently dam-l Original / September 19S0 1
+ -.
(
6 MODEL RDS-l ,,
'To reassemble, reverse procedures. Before tightening aged. The detector can be cleaned by 'using common solvents such as trichloroethylene or methanol. Typical- the set screws to hold the detector, adjust the detector so that the case protrudes 1/16 inch past the housing (item ly, then the desiec is forced air dryed. The contacts to
- the actise area are ultrasonically bonded and can be 11). .
pulled loose if exec >sively strained.
. E. MAINTENANCE ~
Asoid ambients or chemicals containing fluoride .
When cleaning the detector, observe the CAUTION ions. Since the oside used to stabilize the detector.sur- above, To change the filter, remove the filter retainer fape is adsersely affected by the fluoride ion, drastic and old filter. Center the new filter on the O Ring. -
changes in the performance of this desice may occur.
Replac.e the retainer.
- 1. DETECTOR (Refer to Drawing 10748-C01)
- a. Disconnect the RDS 1 from its interface box. NOTE . .
- b. Remove the. clamp nut (ite'm 17). The solid state detector in the RDS-1 is light sensitive.
When the filter paper is being changed, the detector i
connector should be disconnected before remosing the
- c. Remove the filter retainer (item 8).
RDS-1 from its shield.
- d. Remose the center body (item 9).
- c. Loosen the three set screws (item 4).
F. TRO'UBLESHOOTING
- f. Pushing with the cable (item 15), forte the detec-Through the use of the schematic, board component tor out.
assembly, and the section on theory of operation, one The amplifier at.d detector assembly are now shouk. oc able to solve the problems that may be en-exposed. countered.
'- Original / September 19S0 2
6 MODEL RDS.I
- PARTS 1.lST The following iable lists the electronic items incorporated in the RDS-1 and should contain any part necessary for normal electroriic repair. Unicu otherwise specified, callouts of manufacturers and manufacturers' part numbers are to be considered typical examples only and not restrictions against using equivalent parts with the same operating charaet' eristics. When ordering parts from Eberline, specify model numbct, serial number, reference designation and value, or a word description if the part has no reference designation. Eberline will automatically substitute equivalent parts when the one called out by manufacturers' part number is not available.
REF DESIG. PART DESCRIPTION MFR & PART NO. ,
Detector Solid State, Alpha Harshaw DJC-500-50-100B Cl,C2 Capacitor 0.01 pF,80V Sprague 192P1039R8 C3,C4 Capacitor 3.3 F,15V Tantalum CS13B, Case A
~1 CS Capacitor 4.7 pF, ikV Disc Ceramic Sprague 10TCC-V47 C6 Capacitor 6.8 F,35V, Tantalum CS13B, Case B l CRI Diode Current Regulator,0.43mA IN5289 J402 Connector 5 Pin, Male Amphenol 165-33
- Q1 Transistor 1ET 2N5358 Q2 Transistor NPN 2N4124 Q3 Transistor -
PNP 2N4126
, Q4 Transistor NPN 2N4401
.j R1,R2 Resistor 100k,1/4W, 5%
R3 Resistor 470k,1/4W ,5%
i R4 Resistor 2.4k,1/ 4V, 5 % .
~
RS,R8 -
Resistor 5.lk,1/4W, $% .
R6 Resistor 2.7k,1/4W, 5%
R7 Resisto: 18k,1/4W, 5%
R9 ' Resistor 3k,1/4W, 5%
RIO Resistor ik,1/4W, 5%
Ril Resistor 750,1/4W, 5%
KTl Sensistor 10k at 25'C TI TG-1/8 -
Original /Septembe'r 1950 3 M
u . R/
/00< l24VDC]
, vvvv . _
, : A 4 24 voc e5 -
5./K (4 -
'cel . - R8 .
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cf g, C2 Q Q2 20l'29 '
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- t k T f,5,
, <~ tax es q eri -
'g4 gs .e9, .RTi k<750 470k , 0:;. 2.4K 2.7K BK tax 3,3 p . _ . j u ) B GROUA/O .zo O
S'/ J402 p
. x DETECTO2 E -
h Howst
/ syt RES/3702S /A/ 09MS.K=/000
- 2. Ju.l. CAPM/702S /A/M/CAOFABADS EycEP7 sqS AiorED. .
9 5:n .
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W 3
4 5 RDS-! Schematic,10748-BilC. .
o
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5* A/0TES :
E k;' 1 ,a k.
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- 4 - h '- *EUD TQ BoARO .
- ? % gy b"BAUG END TO BoAk'O
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- ct.s rhe , son = 6'4 ( e s. 8 t) C
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ss on ~ (**)
14 1 Sr.e sret ror . Tr
- r=e 4 (.>rr)
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/4 /
- as e#5e17te J w 4e 2 4 (Q a)
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is) I
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A 21 -
c:re.e . tuu&a e rsi g tz o - esw,rw a s r es s,ve <<.., (u) v.
RDS-1 Circuit Boarel Assernbly, 10743-809C. -
1
r 1
MODl!L RDS-l .. )
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go r TOPlu C O
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. ,, $G.CKR MOTL 3. 4 nort A y
- g. DETAll N B oA M D Vin!NG ,
LIOTES *
- 1. APPLY ATHIN UUTC4M CCAT OF l == l +=*= *= l =====**== l LOC TITE To TACACS(ITEMS 1241$ i 2. MW .
0 RauG.he' o = 4 go t = >c s t=* **m m W. /
- O-stuG 2bo o.s2hb.t 2*ow cat.an *M 3,L LluSULATC BARC CRAid W'RC BEFCRE 4 3
$0LCE5lfUG 70'GND* Ou PC.BCAD. S : - stT o.niu:scatw GeOoaa + 6 u.M aucu = N-e c. w.ks =Y.
sc.=s uiE CLEMi viuYL TL'S 4G e i -
o.a. u, 2, i o.s inc c = 43 x .,mq g, A A ADJUST C3.TECTcc GTEM k3)To srsCK. 7 , . senty ,c7,3.xe, ~
CUT t)ic," FAST G MO OF THE CETECTOR g, , , LL,ggg e:tt M rAruER .:Nm. eoo BODY,(ITEM tt )
PcecARO AW Y.-
io746 - t o@
TO THREADS AND CASLC EEFCRE ASSv. is :
- 0,ETE::ca ecev. c 4s-es .
WIFE OFF EX CESS AFTER TIGHTE.Jiuc. . 12 I "_JM.'si o , 'Oc 6 - bid 13 ' *
- "D* '0743 - "d AlCAbtE LEuGTu FRCM CLAMP uuT6 TEM n) I4 1
- CGUUECTOR. AMO* EWL
- eb - M TO CouuCCTOR TiP,1513,*
A e5 (2' CM .E. ELLClu
- s*?: en s.aAL 16' 44
- iCC
- T I T G
- 3 2, 17 i
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- a CL1 EC f GR M t.D FATL aaha*QQ i9 .-
M. l RDS-1.\lechanical Assembly.10743-D0!G.
- Original /Septe:nber 1980 6 ,
e
. W 9
r RDA-XX ~
A. GENERAL DESCRIPTION C. THEORY OF OPERATION -
The RDA radiation detectors are a series of scintilla- When radiation reacts in the crystal, a small flash of
. tion type detectors intended for mstallation in sampler light is generated. The light photons are coupled to the assemblies that monitor radiation in installed systems. photornultiplier tube where they release electroris from The -XX in the model number is replaced by a number its photocathode. These electrons are accelerated along .
and a letter defining the type of scintillation crystal and the dynode stringin the tube, gaining in number at each 8
the housing type. The last X defines the housing: A for dynode, until they reach the anode. The gain is con-
. aluminum. S for stain! css steel. The first X defines the trolled by the high voltage applied to the tube. The crystal: I for ZnS(Ag) alpha,2 for 2 inch x 2 inch Nal number of electrons collected (pulse amplitude) for each (TI) stabilized camma,3 for plastic beta,4 for 2 inch radiation event in the ' crystal is dependent on the x 2 mm Nat . ) gamma,5 for 2 inch x 2 inch Nal (TI) amount oflight generated (type of crystal and radiation gamma. Other types are readily available also. energy) and the high voltage applied.
B. SPECIFICATIONS D. MAINTENANCE I
- 1. Photomultiplier Tube: 2 inch ,10 dynode with Sll 1. PREVENTIVE hlAINTENANCE
.J photocathode. This is a selected high resolution type for ,
pulse height analyzing applications. The assembly does not require any scheduled
. .. maintenance.
- 2. High Voltage: hfaximum 1800V, typically in 600-1200V range depending on application. 2. DISASSEh1BLY AND REAS";Eh1BLY
- 3. Current: 120h10 resistance requires 10 gA at a.' Disassembly
~
1200V.
Removeihe retaining ring at the connector end. Slide
- 4. Connection: Single 51HV coaxial connector sup- the internal assembly out.
plies high voltage and signal connection.
- 5. hiagnetic Shield: Included. CAUTION l
j 6. Scintillation Crystal: The crystalis not attached except
. by the optical coupling com-
- a. -l type: 2 inch diameter ZnS(Ag) with ! mg/cm' pound; do not let it fall.
aluminized mylar window.
- b. -2 type: 2 inch x 2 inch Nal(TI) with '"Am seed Remove the cry:tal from the photo tube. The photo imbedded for aut6matic gain ~ stabilization. tube may be unplugged from its socket.
- c. 3 type: 2 inch diameter x .010 inch thick plastic b. Reassembly l with 1.6 mg/cm8 aluminum window.
Plug the hoto tube into the socket. Place a small
- d. -4 type: 2 inch diameter x 2 mm thick Nal(TI) quantity (approximately 1/4 cm') of optical coupling l
for low energy gamma, stabilized. compound (Dow-Corning 4-X8 compound or equal)
I on the crystal and press and rotate against the photo l e. -5 type: 2 inch x 2 iach Nal(TI). . tube until uniformly seated. Slide the assembly into the housing and install the retaining ring.
- 7. Size: 2.62 inch diameter x 9.25 inches long (6.7 x 231 5 cm), excluding connector. c. 'Crystals .
- 8. Temperature: 0 to 140'F (-18 to 60'C). Refer to the attached drawings for crystal assemblics.
Original / September 19SO 1 y
R DA .XX PARTS LIST The fo!!owing table lists the c!cctronic items incorporated in the RDA-XX and should contain any part necessary for normal electronic repair. Unless otherwise specified, callouts of manufacturers and manufacturers' part numbers are to be considered typical examples only and'not restrictions against usin'g equivalent parts with the same operating characteristics. When ordering parts from Eberline, specify model number, serial number, reference designation and value, or a word description if the part has no reference designation. Eberline will automatically substitute equivalent parts when the one called out by manufacturers' part number is not available. ~
REF DESIG. ' DESCRIPTION htFR & PART NO.
- l. All RDA-XX *
, Connector Assembly Eberline 10661-B05 Connector, h1HV Amphenol 2702S Socket Assembly Eberline 10661-B21 Photomultiplier Tube -
Eberline 10613-A19
- 2. RDA-IX Crystal Assembly Eberline 10661-B18 Phosphor Crystals, ZnS(Ag) -
Aluminized hiylar, Eberline hf-!!
0.00025 inch thick
- 3. RDA-2X
- Detector Crystal, Stabilized Eberlin- 10658-A01
- 4. RDA-3X Aluminized h1ylar . Eberline hi-10 Aluminized htylar Eberline hi-11 -
Plastic Scintillator, Pilot "B" 0.010 inch thick .
S. RDA-4X Detector Crystal Eberline 10661 A24 Stabilization Pulser, . liarshaw AN1145Gil3K-X
- 6. .RDA-3X '
Defector Crystal liarshaw 8DS 2'
. Original / September 1980
. m
I
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M C T M N -
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o O z z z z z z z z z z z > > > > > > > > > 3 x 4 l 4 O O O O O O O O O O M O, il 10 9 8 7- 6 5 4 3 2 1 13 14 o o o o o o o o o 'o o o o t .
R601 R602 R603 R604 R605 'R60G RGO7 R608 R609 R610 R6tl R612 15 6B R601 THRU R610 ARE lOMEGO. MEGO MEGO
! :o o
f- s l .>
N s 'k '
X 4 .< . .
GND HV DETECTOR ASSEfiBLY .
D/A Schematic,10613-BM. .
e 1
RDA-XX .
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e.
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1/sur rief sow-so s 5 . NOTES: . 4 _ Ae ~ crystsss z s cap -
g [1: APPLY ITEM S TO ITEM 3. REMOVE BACKING f l ag ,
o,y,, 33,, y m, , 3y ,, f,g,3
- t/.ATERI AL, MASK OFF ~1/16 ON OUTER EDGE g , , ,, , ,g y ,,, y g ,g ,
g AND APPLY AN EVEN COATING OF ZnS (Ag) 7 , , jfj, , , , ,
. o (ITEM t. AND PRESS FIRM.LY IN PLACE. DUST
/ d 6 4 / ~##5
- EXCESS OFF CRYSTALS . PRESS , TO MYLAR ,
8 / ~ (#fl'A d- "#d'J/" 6 (ITEM G) AND TRIM FLUSH WITH EDGE OF LIGHT
' PIPE. -
I 1 3 4 5 6 7 8 x
.M 4'
x x
03 - .
0 ( i en - - - -y t
(i n.
.i \\\ -
\ / b
\ / s 53 - /
i.
RDA-IX Alpha Crystal Assembly,10661-B18.
to.
e -
peo. ovare. Pepe. Descairviose
/ 3 MJY. Jff JC/fwJ, "C-32 At/faV Nr. x V., *4 c.. D.
., NOTE: 2 /
1/'k! Mr !!!M'r. src c /-#A, A 1. USE DOUBLE STICKY TAPE (9) TO SECURE THE y f -
2fspy jyf,j- , g o a f.,,f o 7 s
BETA CRYSTAL (4) TO THE LIGHT PIPE (3). 4 , . cf y,,.y MAKE SURE THERE ARE NO AIR BUBBLES y y, .y , g, BETWEEN THE WiO. USE.A RING OF DOUBLE -- -
E 'A '
d_#vy 902p i m e -,e STICKY TAPE AROUND THE EDGE OF THE - -
DETA CRYSTAL OPPOSITE THE LIGHT PtPE, 7 ' * >#4 4 /#4 4/-d'4 "
TO SECURE THE M 10 MYLAR. THE M 11 8 ' - (d '>7d 4 "ve'>'"G / 0 4 4 '-er'5 MYLAR IS HELD IN PLACE DY PRESSURE {'g., ') A8 r cous; E s r,e.r r ree- p , 4, o s BETWEEN THE BETA CRYSTAL AND HOUSING. - -
, A a
/ 2 3 -
4 S s 7 9 W
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8 -
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r .
l RDA XX .
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7 Original / September 1980 i . -.
'~
. . _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ - _.1 - _ -
'DA1-1 and DA1-6 -
A. GENERAL DESCRIPTION twisted pair cable. Maximu[n normal cable length is 5000 feet (1523 m). Use 18-gauge wire if cable run is Remot'e Detector Assemtlies DAl-l and DAl-6 are more than 2000 feet. '
Geiger-Mueller (G.M) type detectors. They contain their
- own high voltage supply, pulse amplifier, low voltage 6. MOUNT,1NG regulation and line driver. Low voltage power is sup-plied by the system 12V line. Mounted with four screws through the back plate.
The assembly may also contain a check source 7. CONNECTIONS -
assembly (optional) that is operated remotely. The -
- presence of this option is indicated by a "CC" suffix on Signal output and power input:
the model number,'e.g. DAl 6-CC.
Amphenol 165-11 connector mates with Amphenol The 6nal from the detector is amplified and then 165-10.~
processed by a line driver. The signal is carried on a twisted-pair cable to the microcomputer where it is pro- *
- 8. SATURATION cessed and displayed.
The DAl-1 and DAl-6 differ only in the type of G-M '
tube used and the high voltage generated for those 'DAl Remains operational to lbOG r./n field.
tubes.
C. TIIEORY OF OPERATION B. SPECIFICATIONS 1. GENERAL
- 1. MECHANICAL T'he high voltage section develops the potential ap-plied to the G-M detector. When radiation reacts in the
- a. Size: 9.5 inches high x 3.9 inches wide x 4.85 in- detector, a negative pulse is generated and coupled to ches deep (24.1 x 9.9 x 12.3 cm). the amplifier. This pulse is amplified and coupled to the
~
clectronics channel to. be processed and displayed as
- b. Weight: 2.50 poun's d (1.13 kg). Add 0.25 dose rate.
pounds (0.1 kg)if the check source option is installed. -
- . 2. FUNCTIONAL THEORY
- 2. SENSITIVITY
- a. High Voltage Supply DAl 0.01 to 100 mR/h (approximately 1,200 counts per minute (cpm) per mR/h). Transistor Q204 is connected as a blocking oscillator and gets its feedback for oscillation from DAl 0.1 to 10,000 mR/h (approximately 80 T201. The voltage is stepped up by T201 and fed back cpm per mR/h). -
by V201 and Q206 to control the current of Q204, thus keeping power dissipati6n to a minimum. The high
- 3. LOW VOLTAGE voltage is determined by the voltage regulator (V201).
+ 12V at 50 mA. Optional check source requires
.b. Amphfier '
12V at 2C0 mA when actua'ted.
. . Q210 is an emitter-follower amplifier biased in
- 4. HIGH VOLTAGE the Class A region. When an input pulse occurs, the voltage on the emitter of Q201 decreases by an amount Internal high voltage supply +900V for DAl-1 equal to the magnitude of the input pulse. Pin 2 of A202 and + $00V for DAl-6. (a voltage comparator) is connected to the emitter of Q201 and thus the' voltage on the positive input of the
- 5. OUTPUT comparator also decreases during each input pulse. Pin 3, the negative input of A202, is held at a constant 3.4 VDC (nominal) alternating polarity into a potential by C207. The initial voltage difference be-Original / September 19SO 1
, --r
' DAl 1 and DAl-6 tween Pin 2 and Pin 3 is set by the va' :e of R207 and the If the optional check source is installed, the detector current flowing through it. When the voltage on Pin 2 assembly is shipped with the limit stop set for minimum decreases to a value equal to or less than the voltage at effect when unactuated, and the check source contribu-Pin 3, the comparator turns on and its output goes low. tion to detected counts is masked by background.
After the, pulse, when Pin 2 returns to its initial value, the comparator's output goes high. This action causes 4. TROUBLESHOOTING A2M, a 4 bit binary counter, to register a cotint. Taps Determine if the proper voltages are present. (See the are provided to divide the input count rate by 2,4,8, or ~
- 16. Normally : ' ; divide-by 2 tap is used and input count schematic,10S03-C07.)
rate is reduced by a factor of 2. A2M drives A203, a 500
.line driver, which is connected to drive a balanced For low voltage measurements, use a vohmeter with an input impedance of 20,000 ohms per volt or greater.
twisted-pair line.
- c. Low Vo)mge .
For high voltage measurements, use an electrostatic
- voltmeter or a DVM with a 1000MD probe. If an elec-A201 is an integrated circuit voltage regulator pro- trostatic voltmeter or a 1003MD probe for the DVM is not available, a regular voltmeter may be used for an in-viding a fixed SV odtput. R216 reduces A201's power dication,'if Joading is taken into account.
dissipation.
The voltages should be checked in the following order
- d. Check Source to isolate the failure. All voltages are referred to ground When a check source command occurs (from the . (chassis).
compu:er or Display 111 switch), the circt;it to actuate the check source solenoid is completed. The solenoid ac-
- a. J201, pin A, approximately +12V; pin F, OV tion moves the radiation source to within close prox. (ground).
imity of the detector, pro 4 ding a repeatabic reference
- b. C20S positive, +5 0.2V.
reading. .
- c. .R202-C201 junction (with an electrostatic voltmeter): DAl-1,900 z30V; DAl-6,500120V.
D. MAINTEN ANCE Representative waveforms and other voltages appear
- 1. DISASSEMBLY AND REASSEMBLY on the schematic.
- a. Remove the unit from the mounting plate by Some G-M tube failures cause a multiple-pulse output opening the two latches at the top and bottom of the from the tube. This would appear as a sudden increase assembly. .
in channel reading, especially in low fields. If this condi-
- b. Remove the three O ring screws on the sides of tion is simply calWra:ed out, a probable non-linearity in the assembly. Remove the chassis. Avoid putting undue reading exists. To prove the multiple peing, two stress on the wires. This exposes all circuitry and methods can be used:
(1) Check the senshivity of the G-M tube by connee-mechanisms for maintenance. ting a pulse counter to the output connector, pin D.
With the detector egosed to a known y ficid, the sen.
- c. Reassemblein the reverse order. sitivity should be (approximately) as follows: DAl 1, 600 cprnper mR/h;and DAl-6,40 cpm per mR/h.
- 2. PREVENTIVE MAINTENANCE
. (2) Connect an osci30 scope to pin 7 of A202. Observe Keep the assembly as clean and dry as possible.
Unless the unit is opened regularly, this should be of no the pulses. At low count rates, pulses should occur concern since the operating components are sealed from singly, not in pairs er groups, the environment. No scheduled presentive maintenance is necessary. 5. CABLE RECOMMENDATION
- 3. CALIBRATION .
Cable Length Alpha Bclden Conductor Size No calibration cor.trolis available or necessary on the Less than 2000 ft. 6010 8777 22 AWG DAl 1 or DAl-6.
- 2000 ft.-5000 ft. 6023 9773 ISAWG All calibration is performed by the com'puter soft- .
ware. .
Original / September 1980 2
DAl 1 and DAl-6 PARTS LIST The fo!!owing table lists the electronic items incorporated in the DAl.1 and DAl-6, and should contain any part necessary for normal electronic repair. Unless otherwise specified, callouts of manufacturers and manufacturers' part numbers are to be considered typical esampics only and not restrictions against using equivalent parts with the same operatini characteristics. When ordering parts from Eberline, specify model number, serial number, reference designation and value, or a word description if the part has no reference designation. Eberline will automatically substitute equivalent parts when the one called out by manufacturers' part number is not available. .
R5F DESIG. PART DESCRIPTION MFR & PART NO.
A201 Integisted Circuit Voltage Regulator, +5V, IA Fairchild 7805UC or
. . National LM340T-5.0 A202 ' Integrated Circuit Comparator National LM311H A203 Integrated Circuit Quad NOR 500 Texas Instruments L.ne Driver SN74128N A2M Integrated Circuit 4-Bit Binary Counter Texas Instruments .
SN74LS293N C201 Capacitor ,. 220pF, 3kV CRL DD30-221 t*1 C203 Capacitor 0.1 pF, 8.0V Sprague 192 PIN 9R8 C2M Capacitor i . 3.3 F, ISV, Tantalum CS13, Case A C205, C2% Capacitor 0.01 pF,2kV Sprague BL-510 C207 Capacitor 0.1 pF, 35V,' Tantalum CS13, Case A C208, C209 Capacitor 120 pF,10V, Tantalum CS13, Case C C210 Capacitor 2.2 pF, 20V, Tantalum CS13, Case A .
C211 Capacitor 0.01 pF, 200V Sprague 192P10392 l CR201, 203 Diode Silicon IN4148 CR2N, 205 CR202 Diode 2500V PlV Varo VA-25
(
. Q201 Transistor PNP, Silicon 2N4126 l - ..
PNP, Silicon Q204 Transistor 2N4234 Q205, Q206 Transistor NPN, Silicon 2N4124
~
R202 Resistor 330k, 10To,1/4W i
[ R203 Resistor ik,110Va,1/4W t
R2N . Resistor 20k, il0?o,'l/4W R205 Resistor 30k, i 10%,1/4W R206 Resistor 1.3,k, i 10To, !/4W ,
Original / September 19SO ,
3 l
DAl 1 and DAl-6 REF DESIG. PART DESCRIPTIO MFR & PART NO.
~
R207 Resistor 200, STo,1/4W R208 Resistor . 39k, 10To, f/4W R209 Resistor 270, 10To; 1/4W ,
R210 Resistor 6.8k, 10To,1/4W .
R211 Resistor 3k, STo,1/4W R212 . Resistor 330, i10To,1/4W ,
R213 Resistor 22M, 10To,1/4W R214 - Resistor 470k, 10To,1/4W R215 Resistor 10k,110To,1/4W R216 Resistor 43, STo,1/2W
.T201 Transformer Blo'cking Oscillator Microtran M8149
. O-Ring Housing Sea} Eberline 10031-A176
. t
- 1. DAl-1 V201 High Voltage Regulator' 900V Corona Tube Victorcen 5841 or GV3A-900
~
V202 Detector G-M Tube Eberline 10450-B12
' 2. DAl-6 .
R201 Resistor 10M,110To,1/4W V201 liigh Voltage Replator 500V Corona Tube Victoreen GV3B-500 V202 Deteetor G-M Tube, Eberline 10450-B28 j
. Energy-compensated
~
4 ,
Original / September 1980 k
- 6 DAl 1 and DAl-6 ..
M
' Check Snurce
> (Optionall .
SfGNAL yI Geiger Mue'fer _.--> AMPLIFIER S LINE DRIVER Tw.sted pair
. DET ECTO R a6 Cable o
It n
~
. _ . . - - - - .. - - - - . LOW VOLTAGE , ,
, , POWER REGULATOR INPUT
[ .
db a -'
1r .
- System Block Diagram,10803-A14.
.2
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!L e .: ! -
NO3LE GAS DETECTOR A. GENERAL DESCillPTION 6. Environment: Operating temperature range -40'F The Noble Gas Detector assembly.is a beta-gamma detector intended for use in sampler assemblies. The 7. Connector: BNC series. detecting element is an argon-filled, halogen. quenched Geiger Mueller (G M) tube mounted in a holder which S. Size: 2.75-inch (7.0 cm)* diameter x 8.!! inch . forms part of the shield when installed in a sampler.The (20.6 cm) length. detector assembly is connected to a microcomputer syste'm via an IB-4A interface be c. . 9. Weight: Approximately 6 pounds (2.7 kg). B. SPECIFICATIONS , C. OPERATION
- 1. G-M Tube: A gon filled, halogen-quenched, The Noble Gas Detector assembly is operational when energy. compensated. connected to a functioning IB-4A interface box. No adjustments are available. .
- 2. Operating Voltage: 550 c50V. , ,
- 3. Sensitivit'y: Approximately E0 cpm per mR/h in a D. MAINTENANCF, The Noble Gas Detector assembly requires no
., 4. Dead Time: Approximately 20 microseconds. scheduled maintenance. In general, keep the device as clean and dry as practical.
- 5. Plateau: 100V minimum length with slope approx- '
.imately 15 percent per 100 volts. . .i 3
f 1 Original /, September 19S0 e
NOBLE GAS DETECTOR .
. PARTS LIST .
The following table lists items incorporated into tiie Noble Gas Detector assembly and should contain any part necessary for normal repair. Unless otherwise specified, callouts for manufacturers and manufacturers' part numbers are to be considered typical examples only and n'ot restrictions against using equivalent parts with the same operating characteristics. When ordering parts from Eberline, sp cify model number, serial number, reference designation and value, or a word description if the part has no reference designation. Eberline automatically substitutes equivalent parts when one called out N / the manufacturers' part number is not available. . REF DESIG. PART DESCRIPTION MFR & PART NO. Prote Cover Eberline 10942 B03 . Foam Pad Eberline 10942-A06 G-M Tube Eberline IG450-B28 Grounding Sleeve Eberli.te 11032 AI7 Insulator Eberline 10942-A04 Probe End Eberline 11032-B16
' Resistor ,
10M,1/8W, 10 % O-Ring 3/4 inch ID x 15/16 inch OD Parker 2-116 BUNA-N x .103 inch O-Ring 1/2 inch ID x 5/8 inch OD Parker 2-014 BUNA-N x .070 inch . O-Ring 2-1/2 inch ID x 2-3/4 OD ' Parker 2 230 BUNA N x .139 inch , 0-Ring 3/16 inch ID x 3/8 inch OD Parker 2-106 BUNA-N x .103 inch l Wave Washer Seastrom 5S06-60-1
- Retaining Ring TRUARC N5000-81 Original / September 1980 2
P
NOBLE GAS DEirECTOR ,
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+
SA-9
" A. GENEllAL DESCRil' TION C. CIIECK SOURCE OPERATION
- The Model SA 9 sampler assembly comprises a lead.
shielded detector and a length of tubing which deter. NOTE
- mines the sample solume. The SA-9 is used for the
- sampling of gaseous or liquid effluents. The detector is
- an energy-compensated Geiger.hlueller (G 51) tube The ~ check source contains a
. licensable quantity of radioactive which views a section of one-inch outside diameter material (.5 pCi of "Sr"Y).
(o.d.) stamless steel tubing. This section of tubing acts. as the sampic volume. The sample tube can be changed
- When a check source command is requested, voltage to one of another diameter and the distance between the is applied to the t. heck source solenoid. Rotary action of detector and the sample tube varied; either of these changes alters the detector sensitivity. The one-inch tub- the solenoid moves the radioactive source in line with a
., ing is staridard and serves as the basis for calibration. small hole in the detector mounting block. The beta Any alterations to adjust detector sensitivity should be radiation from the source, which is normally sh'elded done by Ebertme. Proper operation of the detector and from the G hl tube detector, shines through the hole, counting circuitry may be verified by actuation of the striking the detector and causing an up-scale reading.
Removal of voltage to the solenoid a!!ows the solenoid check source mechanism which is installed in the SA-9. . spring to return the. radioactive source to its normally A hiodel IB-4A interface box is used to connect the shielded position. SA-9 sampler assembly to either digital- or gnalog-based monitoring systems.
. B. SPECil ICATIONS 1. DETECTOR OR CHECK SOUP.CE SOLENOID ' ACCESS
- 1. MECHANICAL The G-h1 tuba detector and check source are mounted
- a. Shielding: 3-inch (7.62 cm) thick lead. in the same assembly. To access this assembly, the 3-inch-thick lead shie!d (opposite the sample tube) must
- b. Sample Vu/ume: Dependent upon tube diameter, be removed. This shield is h61d in position by four s
. 3/8-16 hex b'olts. Once the shield is removed, the detec-
- c. Sample Tube I inch o.d. x .032 inch wall tor assembly may simply be pulled from the center stainless steel hydraulic grade tubing (standard). shield.
- d. Connections: Stainless steel "Swa::clok" com. NOTE: When rep! acing the lead shield, make sure the pression type tube fitting, inlet and outlet. detector and solenoid wires are dressed into the slot in
- the shield.
- e. IVeight: 'Approximately 315 poundt (143 kg).
- 2. CALIBRATION SOURCE (EIC #11058-00) l f. Si:e (with IB-4A mounted): 13.5 inches long x -
! 13.0 inches wide x 13.7 inches high (34.) cm x 33.0 cm x The calibration soure.e rivailable for the SA 9 sampler 34.8 cm). assembly is a one-in:h o.d. tube sealed at both ends and l con;aining a knokn concentration of "Kr gas. The
- 2. ELECTRICAL calibration source must be inserted in place of the j ' , , sample tube.
i a. Dctccior High Voltage: 500 VDC (supplied by l IB4A). Remove the four 3/S-16 hex bolts holding the 4-inch lead shield in place. The shic!d may then be moved to
, b. Solenoid Voltage 12 VDC (standard). clear the fittings on the sample tube. Once the rampic l
i i . i . 1 Original / September 19S0 I T
SA.9 . , ,. I tube is removed, replace the 4. inch thick lead shield and E. PARTS LIST secure it in place with at least one of the 3/816 hex bohs. This ensures proper calibration source geometry. There are only two spare parts for the SA.9 sampler
. Insert the calibration source into the slot in the 4 inch assembly. ,
shield fr9m either side of the sampler assembly. PART DESCRIPTION t w o B2s c M Tube CAUTION ,
. Do not handle the stainless steel section of the calibration source. ,
- Carry it by the aluminum end .
cap'. . t Original / September 1980
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. l . l ~
SA-11' l
" GENERAL DESCRIPTION A. .
The Model SA-11 detector ' assembly comprises a lead-shielded detector which views a duct or pipe for gamma radiation. The detector is an energy-compensatea Geiger-Mueller (G-M) tube. Proper. operation of the detector and counting circuitry may be verified by actuation of the check source mechanism which is installed in the SA-11. , B. j'CCIFICATIONS .
- 1. MECHANICAL
- a. Shield.ing: 3-inch (7.62 cm) th'ick lead
- b. Weight: Approximately 220 pounds (100 kg) l c. Size (with IB 4A mounted): ,
,i 10.5 inches long x 13.0 inches wide x 13.7 inches high I (26.7 cm x 33.0 cm x 34.8 cm)
- d. Mounting:
Mounts to a flat surface with four 1/2-inch bolts through the mounting plate.
- 2. ELECTRICAL ,
- a. Detector High Voltay;: 500 V DC -
- b. Sole'noid Voltage: 12 V DC (std.)
,
- e C. CHECK SOURCE OPERATION
- NOTE The check source contains a licensable quantity of radioactive material (0.5 pCi of 90Sr90y), .
- When a check source command is requested, voltage is applied to the check source solenoid. Rotary action of the solenoid coves the radioactive The beta source in line with a small hole in the detector mounting block.
radiation from the source, which is normally shielded from the G-M tube detector, shines through the hole, striking the detector and causing an up-scale reading. Removal of voltage'to the solenoid allows the solenoid spring to return the radioactive source to its normally shielded position. e e e e 1 01750/8-31-8'1
SA-11 .
. D. MAINTENANCE
- 1. DETECTOR OR CHECK SOURCE SOLENDID ACCESS -
o The assembly. G-M tube detectdr and check source.are mounted in the This shield is held in, position by four 3/8-16 hex must be removed.Once the shield is conoved, the detector assembly may head bolts. simply be pulled from the center shield. lead shield, make sure the detector and solenoid NOTE: When replacing thia . wires are dressed into the slot in the shield.
- 2. C'ALIBRATION l
i Primary calibration of an SA-11 was performed and is recorded as
- Eberline document number 12000-02. ,
l E. PARTS LIST _ - There are onif two spare parts for the SA-11 detector assembly. Description Part_ G-M Tube 10450-B28 l l Solenoid Ledex H-1079-032 i -- . . . . e e o O . 4 e e
- O 9
e o e
- 2 0175B/8-31-81 I
r
- SA-13 .
r . , 4 A. GENf'.RAL DI'.SCRIPTION 3. CONNECTIONS The SA 13 sampler nu ably affor[is combined par- 1.00 inch (2.54 cm) o.d. stainless steel tubing, ticulate, iodine, noble gas and gamma background "Swagelok" compression fittings recommended.
- . monitoring in one lead-5Maded assembly. Three inches
- of lead shielding are provided to reduce the effect of 4. hf ATERIAL
- ambient gamma radiation; one inch oflead between in- .
- dividual samplers reduces the effect of one sampler on a. Allinternal parts and plumbing: stainless steel. ~ ' another detector. The SA.13 includes two energy-compensated Geiger-Niaeller (G-51)' tube detectors b. All seah: Buna-N.
which are used for mid-range noble gas and gamma background measurement.
- c. G-h1 tube cover (mid-range gas): Nylatron.
j Normally, beta scintillation detectors view the par- d. Beta windows: htylar. ticulate and low range gas samples, while a stabilized gamma scintillation detector views the iodine sample. It
- e. Outer case: 1020 steel, .104 inch (2.64 mm) thick.
.3 should be noted that " low" and "mid range" noble gas I measurements'use the same sample volume but with dif- 5. WEIGHT ,
- ferent detector sensitivities. ..
Approximately 900 pounds (409 kg). Add ap-The SA 13 also accommodates an optional solid state proximately !80 pounds (81.8 kg) for 4 Pi shiciding. alpha detector to subtract radon daughter' background from the beta particulate measurement. 6. SIZE Check sources are availabic for the beta particulate, 17.75 inches long x 15.25 inches wide x 13.50 in-iodine and noble gas channels. ches high, including tubing (45.08 cm x 38.74 cm x
. 34.29 cm).
B. SPECIFICATIONS C. OPERATION .
- 1. SA51PLING NIEDIUh1 NOTE
- a. Beta particulate j .
Normally the three sampling sta-2 inch (5.03 cm) d.iameter fixed filter: Holl- . tions of the SA-13 are connected ingsworth Hose, Type H 70 recommended, or with for series sample flow. The radon subtraction (47mm dia.): hiillipore SS1 recom- pluinbing ' connections to each mended. . sample station are external so that a change in flow path (such
- b. lodine .
as direction of flow through the filter)can be accomplished easily. Sinch (5.0S em) diameter x 3/4-inch (1.90 cm) .. The foHowing text describes the
- thick, metal-cated cartridge containing approximately most common station configura-65 cm' of teda impre;'nated activated charcoal. Eberime tion: Particulate, Iodine and No-No. IC-1 recommended. ble Gas hicasurement with Radon Subtraction.
- c. Gas
- The particulate sampling station is on the left as the SA-13 is viewed from :he front. (The serial number tag l 17.2 cu. in (2S! cm') volume
' is on t'he front). The sample enters the front tube and is 2;SillELDING drawn through the particulate filter. The filter is held in position by the RDS-l alphr radon detector and is in a 3 inch (7.62 cm) Jead mMimum (4 Pi shield fixed geometry between the RDS-1 and the RDA 3X asailable). I inch minimum betwcen individual sample beta detector. Since the alpha radiation cannot station 3. penetrate the filter paper, particulate is deposited on the 1 Original / September 19SO .
~ * .- , ,
V SA13 side of the paper facing the alpha detector. The beta 1. FILTER Cl!ANGE radiation must therefore ran through the filter paper
- and the baeking screen before it reaches the beta.scin- To change the filter on the iodine charcoal cartridge, tillation dereetor. This decreases beta detector sensi- loosen the thumb screws and swing the retainer aside.
tivity somewhat, but the ability to measure radon Pull the filter holder assembly from its shield. Unscrew daughter background negates the decrease in beta sen- the cap and change the cartridge or filter paper. Replace ' sitisity. If radon subtraction is not installed, air flow the holder assembly in the shield, position the retainer through the filter paper is resersed, causing the par- and tighten the thumb screws. ticulate to be deposited on the beta detector side of the filter paper. To change the filter on the RDS-1, fo!!ow the same
- procedure as that noted above to remove the fitter The iodine sampling station is to the right of the par- holder assembly from the shield. To remove the cap,
- ticulate sampling station (center of the SA-13). The simply pull it off. Avoid twistir.g the cap, since this can sample exits the particulate filter and is drawn into the tear the filter paper. Use care to center the millipote iodine'sanipling station. There it passes through a char- filter on the 0-Ring when replacing the cap.
coal cartridge which is vicMd by a garnma scintillation detector. The charcoal cartridge is held in place by a 2. RDA XX DETECTOR CHANGE removable cartridge holder and is in a fixed geometry with the RDA 2X detector. Opec 4-Pi shield doors, if installed. Remove the clamp 'and gently pull the detector from the shield. The sample exits the iodine charcoal cartridge and is O-Ring pressure and tight clearances may make this dif-drawn into the. noble gas sampling station. This is a ficult. If necessary, use the bail attached to the back fixed, cylinder-shaped volume viewed at one end by a plate of the detector as a handle to pull with. Replace by beta scintillation detector (RDA-3X). The other end of pushing the detector into the shield to the mechanical the cylindet is a lead plug which supports lhe,mid-range stop and replacing the clamp. roble gas detector. This detector is located on the center line of the gas volume cylinder and is surrounded by the 3. hilD-RANGE GAS DETECTOR CHANGE sample.
. Loosen the thumb screws and swing the retainer An energy-compensated .G-h1 tube mounted on the aside. Pell the detector assemb!y from the shield.
rear of the. SA-13 extends into the lead shield. This Unscrew the detector cover, unplus the G-hl tube and detector is located on the same side of the SA 13 as the replace it. Reverse the procedure for installation, noble gas sampling station and is used to measure am- making sure the retainer is in place and the thumb bient background gamma radiation. This meawrement screws t.re tight. . can be used to correct for contribution of background radiation in the particulate and noble gas 4. BACKGROUND DETECTOR measurements.
. Open 4-Pi shield doors, if installed. Remove the four D. StAINTENANCE 4-40 screws that hold the BNC bulkhead connector to the SA-13. Remove the connector / detector assembly. , Unplug the G-h1 tube and replace it. Reverse the pro-NOTE cedure for installation.
The air flow pump should be stopped before attempting to remove filter holders or detec. tors. 2 , Original / September 1980 6 w m
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- SECTION 3 CALIBRATION This procedure assumes that each subasserbly has been tested and calibrated. A good working knowledge of system components and,their interconnection is required prior to proceeding. The following procedure assumes the SPING-3/4* . is , equipped with the High Range Noble Gas Option ;0ption' #1). If your monito'r does not h4ve this option ignora steps indicated with "*."
' - A. METHOD 1 " ~
Since the background subtraction capabilities of the SPING-3/4 can cause some interaction between detector channels and the effects of ambient background to the calibration of given detector, the following procedure
- minimizes error in calibration.
h. j, 1. DETECTOR QUALITY , Before the actual calibration process is begun, detector quality and control settings should be proven and/or reset. Use the forms and graphs in your calibration and checkout data package for reference. The appropriate IB-X manual section explains all their controls and i settings fully. -
~
- a. Beta Detectors (Particulate and Low Rance Noble Gas) (RDA-3A)
Run a plateau of counts per minute (cpm) vs high voltage. These data should. compare very closely with the data provided in your data package if a comparable 90S r-90Y source is used. Set the high voltage on the plateau region below the increase in .
.. background count rate. -
1 Complete checkout of an RDA-3A and an IB-2 can be performed t utilizing the following Eberline checkout procedures. SUBASSEMBLY CHECK 0UT PROCEDURE IB'-2 10429-All3 "RDA-3A 10429-A220 " RDA-3A with 18-2 10429-A232 ,
- b. Alpha Detector (RuS-1) ,
Using a 230Th 53urce, run a pulse height spectrum of cpm vs. threshold setting. These data should compare very closely with the data in your data package when referred to energy (threshold volts). Note that the data supplied have thresuold voltages o e i D e J
. - mpg n - - >. i
. SPING 3/4 .
CALIBRATION ,
' calibrated to alpha energy. Calibration.of energy to threshold' voltage is accomplished by adjusting the gain control on the .
amplifier board. . Complete checkout of an RDS-1 and a IB-3C can be performed utilizing the following Eberline checkout procedures.
. SUBASSEMBLY ' CHECKOUT PROCEDURE .
RDS-1 10429-A228 IB-3C 10429-A133 RDS-1 with IB-3C 10429-A229
- c. Iodine (RDA-2A)
Run a pulse height spectrum of cpm vs. threshold volts. The data should exactly duplicate the data provided in your data package when referred to energy. The threshold must be
. calibrated to energy for use later in the calibration procedure.
Complete checkout.of an RDA-2A and an IB-2 can be performed utilizing the following Eberline che:kout procedures. SUBASSEMBLY CHECK 0UT FROCEDURE . IB-2 10429-All3 RDA-2A 10429-A219 IB-2 with RDA-2A 10429-A231 ,
- d. Gamma Detectors '(Medium Range and High Range Noble Gas, Area Monitor and Gamma Backgrouno)
The gamma detectors listed above are all energy-compensated G-M tube type detectors which, when connected to their interfacing electrbnics (IBs), have a known sensitivity (in air) to a given gamma field. The followir.g list depicts by channel designation
- the Eberline G-M tube type, its nominal sensitivity, interf acing electronics and Eberline checkout procedure number.
NOTE: 'The sensitivity is the count rate out of the electronics and not the G-M tube sensitivity. i 4 r
~ '
SPING 3/4 CALIBRATION -
' Interfacing EIC Sensitivity Checkout C_hannel Designation GM Tube Number CPM /mR/hr Electronics Procedure Medium Range 10450-B28 40 IB-4A 10429-A255 Noble Gas *High Range. 10450-B28 40 IB-4A 10429-A255 . Noble Gas , ,
Gamma Background 10450-B28 40 , IB-4A 10429-A255 a
'! Area Monitor 10450-B12 600 Part of 104~9-A137.
Detector lJ (DAl-1) Assembly The checkout procedure for an IB-4A is 10429-A195. t -. i 2. CALIBRATION (utilizing,the microcomputer) ,
!, The following procedure requires editing each channel file three times. The first edit adjusts each channel for a calibration constant of 1.00E + 03 ar.d no subtraction. The readings for each channel are then output as cpm from their. associated detector. The second edit is performed af ter fixed background rates are determined and factors for background measured by other channels are deter-mined. This then provides the proper point to attermine channel ,
calibration constants. Af ter calibration constants are determined,
.the background, subtraction measurement for radon is determined. At -- this point the third edit of channels is performed and the SPIriG-3/4 l*' is calibrated. During the third edit the remainder of each char.nel fil can be edited to include selection of alarm setpoints, sample flow rate and automatic logging. 1st, 2nd and 3rd Edit Data Sheets are provided at the end of this section. Copies may be made to aid.
in calibration. Af ter the unit is calibrated, it is helpful to retain the final edited channel parameter' file print-out for each
- channel. This' printout can also provide historical documentation of
! actual value used by the monitor for that time period.
. 3. FIXED BACKGROUND
- a. Flip the calibration switch to ON and turn the pump 0FF. Note that calibration switch forces a printout of data on each channel every 10 minutes. -
- b. From the Control Terminal, perfoM the First Edit of all channel files within the unit being calibrated for the following:
Units = cpm (ent;er 03 af ter menu of units is typed on editing line.02) \
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! SPING 3/4 - l . CALIBRATION Calibration Constant = +1.00+00 .
. Skg.1 and 2 Ch. No. = 0 ,
Bkg. I and 2 Factor +0.00+00 .
~
Fixed-Ekg. SUB = +0.00+00 -
, See 1st Edit Data Sheet.
- c. Place new, clean filters in the particulate channel and iodine
' channel. The sampler may be purged with nitrogen or radioactive-free air at this time to reduce any residual radioactive deposits.
- d. Disconnect the particulate, iodine and low range gas channels detectors (1, 3 and 5) at their interface boxes. Command the check s'ource for channels 1, 3, and 5 This procedure shields the check sources from the area detector (Ch. 6). Under these conditions, ambient background, as well as a fixed background subtraction for the area monitor, can be determined as follows:
1) Allow 20 minutes to elapse (2 printouts on the Control Terminal's printer);' then record the last printout for Channel .6,. Label this value "A." Record the last printout for Channel 8. Label this value "B."
'2) Reconnect the detectors for channels 1, 3, and 5. Wait until check sources have retracted; then wait for the ,
second printout of data with calibration status. Record the last printout for Channel 6 and label this value "A1." Record the last printout for Channel 8 and label this value -
"Bl."
- 3) Value "Al" minus value "A" = CONTRIBUTION FIROM CHECK SOURCES which should be entered as the fixed subtraction ra'e t for Channel 6.
Record this vaiue in spice 6-1 on the 2nd Edit Data Sheet'. Value "Bl" minus value "B" equals CONTRIBUTION FROM CHECK 5OURCES which should be entered as fixed subtraction rate for Cnanoel'8. Record this value in space 8-1 on the 2nd Edit Data Sheet. NOTE: If results are negative ignore and enter values of
. 40.00+00. ,
NOTE: The contributions from fixed radiation (cosmic rays and/or contamination in the shielding naterials) ara generally relatively low compared to high ambient gamma levels. If the final installation of the SPING-3/4 is in a
. nigh , ambient background (i.e.,1.0 mR/h or above), effects 9
e
.e
SPING 3/4 , CALIBRATION
~ '
of the fixed background contribution are of little conse-quence for the final measurement. Under these conditions, further corrections fJe fixed background subtraction can .be omitted by going to step 4. The data may still oe optimized under these conditions by elevating the ambient background and determining the count , rate ii; a channel of interest (as in step 4) and then - projecting that reading to actual ambient. The zero offset from this calculation will be a fixed rate that should be subtracted on the particular ch.annel. p-
- e. Obtain th'e'last printout for Channel 1 (beta particulate). This
' J number is both the fixed background and the contribution from f ambient. Assuming that 95 percent is fixed, multiply this value by 0.95 to obtain fixed subtraction rate. Recora this value in space 1-2 on the 2nd Edit Data Sheet. !.. Repeat the above procedure for Channel 5 (low range noble gas) -
by obtaining the .last printout for Channel 5. Record the
- adjusted value in space 5-2 on the 2nd Edit Data Sheet, cpm x i
0.95. .
..' Repeat the above procedure for Channel 7 (mid range noble gas) by obtaining the last printout.for Cnannel 7. Record the adjusted v'alue in space 7-2 on the 2nd Edit Data Sheet, cpm x 0.95. - ~
- Repeat the above procedure for Channel 9 (high range noble gas)
. . by obtaining the last printout for Channel 9. Record the adjusted value in space 9-2 on the 2nd Edit Data Sheet, cpm x 0.95. ,
Enter.the following values for fixed background subtraction from
,the 2nd Edit Data Sheet by editing the ' associated channel parame+ar fila. -
- 1) Value in space 1-2, into Channel 1
- 2) Value in space 5-2, into Channel 5 -
- 3) Value in space 6-1, into Cha'nnel 6
- 4) .Value in space 7-2, into Channel 7.
- 6) Value in space 8-1, into Channel 8.
- 6) Value in space 9-2, into Channel 9.
- 4. FLUCTUATING BACKGROUND
- a. At'this point, determine the factors for background measured by other channels. '
- ~- - - . . . ,
l
$ PING 3/4 l CALIBRATION ,
Iodine (Ch. 3) uses an adjacent energy. window (Ch. 4) as its background measuring source.131 Channel 4 is set to measure an 1 energy. Scatter from higher equal window just above the energy gama smears through both windows approximately equally, so b"ckground in both' windows will be equal except for the slope of the scatter through those windows. The factor corrects for , this. . Ga :na background (Ch. 8) is utilized as a background measuring source for the noble gas _ channels. The measuring device is an energy-compensated G-M detector similar to the ones used in the mid and high range noble gas channels. It is located in the . rear of the le'ad shield assembly (SA-13). An external gamma radiation field will contribute to the readings of the beta detectors used for particulate (Ch. 1) and noble gas measurements (Ch. 5) and the gamma detectors used for. mid and high range gas measurements (Ch. 7 and Ch. 9). The gamma background detector -(Ch. 8) is used to. measure the external gamma field.to subtract from the beta particulate detector (Ch.1), the beta gas detector (Ch. 5) and mid and high range gamma gas (Ch. 7 and Ch. 9) measurements, i l) Obtain data from Channel 3 and fabel "C."
- 2) Obtain data from Channel 4 and label "D." ,
NOTE: During[f and 9 steps actory calibration, b.2), 3), background
- 4) and 5) below) factors for are not calcalated. AnyChannels 1, 5, values calculated would not be correct for the local conditions at
- the monitor's ultimate location. The factory calibration provides a conservative measurement since the contribution from ambient back-ground will increase the detected radiation values. To nullify the effects of fluctuating ambient background radiation, the background f actor.s should. be measured, calculated and entered into the channel '
parameter files as follews:
- b. Elevate the external fieid at each de.tector by 50 or 100 times ambient (i.e. if ambient equals 0.03 inR/.h, use a 1.0 mR/hr field). For best results, use a source with an energy which will approximate the energy of the ambient source of radiation.
Wcit for at least two printouts and use the last printout.
- 1) Elevated background channel readings. .
a) Obtain data from Channel T and label "E." b) .Cbtain data from Channel. 5 and label "F." e 6- - em
* *+e me - 4
~
SPING 3/4 CALIBRATION .. i *
"G.",
c) Obtain data from Channel 6 and label , d) Obtain data from Channel 3 and label "Cl." .. e) Obtain data from Channel 4 and label "DI."
., f) Obtain data from Channel 7 and label "H." "I." .- - g) Obtain data from Channel 8 and label *h) Obtain data from Channel 9' and label "J."
- c. At this point, calculate the fixed background subtraction factor
.I and the background factor for Channels 1, 3, 5, 7 and 9 as follows: .. ..
- 1) Channel 3
- ... a) Value Cl = factor for Channel 3 BKG #1 Value D1 ,
Record in space 3-1 on the.2nd Edit Data Sheet.
. b) Value D from 4.a.2) above multiplied by the factor for Channel 3 a) above minus Value C from 4.a.1) above, i.e., -[(Value D x f actor for Ch 3 BKG #1) 'Value C]
equals the fixed subtraction fcr Channel 3. ,, If the result is negative, record a zero; if the result is positive, record it in space 3-2 on the 2nd Edit Data Sheet. i.. -
- 2) Channel 1 ~
Value E = factor for Cha*in.el 1 BKG #2 Factor
~
Value 1 Record in space 1-1 on the 2nd Edit Data Sheet. ,
. 3) C.hannel 3 .
Value F = factor for Channel 5 8KG fl Factor ialue I Record in space 5-1 on the 2nd E'dit Data Sheet.
- e e
.).
- SPhNG3/4 .
CALIBRATION
- 4) Channel 7 ,
Value H = factor for Channel 7 BKG #1 Factor Value I . Record in space'7-1 on the 2nd Edit Data Sheet. ,
*5) Channel 9 - Value J = factor for Channel 9 BKG fl Factor Value I Record,in space 9-1 on 2nd Edit Data Sheet.
- 5. SECOND EDIT ,
Enter' all values from t$e 2nd Edit Data Sheet by editing Channels 1, 3, 5, 6, 7, 8, and 9 channel parameter files.
- 6. CALIBRATION CONSTANTS . .
At this point, calibration constants can be determined.
- a. The area monitor (Ch. 6) calibration constant can be determined by data taken in step 4.b.1)c), .Value G. The' field intensity in mR/h, divided by count rate, equals the calibration constant (use intensity in 'R/h for calibration constant in R/h). ,
. EXAMPLE:'
If the count rate obtained in 4.b.1)c) is 1200 cpm and the field intgnsity is 2.0 mR/h, then 2 mR/h divided by 1200 equals 1.67 x 10-3 for, the calibration constant, if. units are mR/h. Record ' this value in space 6-2 on the 3rd Edit Data Sheet.
~
- b. Noble Gas Monitors (Channels 5, 7, and 9) may be calibrated only with a'known concentration of gas, or by utilizing the calibration techniques in Method 2. Fill the sampler assemblies (SA-13 and SA-9) with a known concentration of gas. Wait for i
two printouts (minimum) and obtain the data frca the last printout. Concen- tration of the sample divided by the count . rate obtained equals the calibration constant.
. 1) Low Range Noble Gas .
EXAMPLE: Channel 5. The following data were obtained by Eberli.nc using known concentrations of 133Xe and 85K r in air: (
. SPING 3/4 CALIBRATION 25 cpm for 1 x 10-6 uCi/cm3 of 133Xe ~
52 cpm for 1 x 10-6 uCi/cm3 of 85gr . NOTE: ' Count rates are at the dete*ctor. Note that the
. 18-2 or IB-4A counts down by two. With the monitor calibration factor at 1.0, the apparent count rates would
- be 12.5 cpm and 26 cpm, respectively. ,
' t' a With the sampler filled with 1 x 10-4 uci/cm3 of 85 Kt , .. a count rate of 2600 cpm was obtained. S6:
1 x 10-4 pCi/cm3 divided by 2600 cam equals a calibration constant of 3.85 x 10-0 uC1/cm3 cpm. /
;' With the sampler filled with 2.2 x 10-4 uCi/cm3 of 133X e, a count rate of 2750 cpm"was obtained. So:
2.2 x 10-4 oCi/cm3 divided by 2.750 cpm equals a *
;'. calibration constant of 8.00 x 10-8 uCi/cm3/ cpm. ;; Under operating conditions, this calibration constant can . . and should be manipulated to agree with laboratory determinations of the concentration and isotopic mix of the sampled gas using calibration Method 2.
After determining the calibration constant, record the value in space 5-3 on the 3rd Edit Data She'et.
- 2) The calibration constants for Channel 7 and Channel 9 are determined in a similar manner with their constants entered on the 3rd Edit Data Sheet in spaces 7-3 and 9-3,
. respectively. , ,
L .
- c. The Iodine monitor (Ch.3) measures the 364-kev energy emitted by 131 1 Since 131 I is an impractical calibration standard, l
133B a is used as the calibration standard. The gamma energy ' i of interest of 133B a is 356 kev, so the IB-2 FHA /Line Driver threshold must be adjusted accordingly.
~
NOTE: The voltage measurements ar'e taken between common ("C,"
. grey test point ) and threshold ("THLD," green test point).
, Adjust the threshold (THLD) control. The voltage divided by 2 equals the ener y. The threshold voltage plus one-half the ,. . window voltage Threshold volts + (window volts.x .5)] divided l by 2 equals the energy of the peak in MeV.- t Adj0st the threshold for 0.662 volts to center the analyzer on the 356 kev peak. Place the 133 B a source .in the filter holder ( so it is closest to the detector. Wait for two printouts (minimum) and obtain data frorb the last printout. Label this *
-g-l ~ . .
4
- SP! fig 3/4 CALIBP.ATION data "K." Remove the 133 8 a source. Readjust the energy window for 1311 (THLD = 0.678 volts). .
The data obtained must now be corrected for the gamma abundance ratio of 133 8 a (69 percent) to 131 1 (82' percent). This - correction factor (0.82 divided by 0.69) is 1.19. Therefore, data "K" maltiplied by the correction factor is the count rate that would be obtained if the source had been 1311 of the same activity. Label this result "Kl." .- EXAMPLE: 1-7/8 inch (4.76 cm) dia. (active area) 133 8a source, 0.0531 vCi Count rate obtained = 2175 cpm'("K")
. 2175 x 1.19 - 25E8, cpm ("K1") -
Value "K1" divided by the activity of the source would then result in the sensitivity of the d'etector if all the iodine were on the front surface of the charcoal cartridge. Under operating conditions, iodine would probably be evenly distributed through the cartridge, so the reduction in the efficiency must be ' corrected for.
. Prior data indicate that deposits at the center of the cartridge . yield 60 percent of the front surface value and the deposits at rear surface yield 42 percent of the front surface value.
Assuming an even distribution, a correction factor of 0.74 must ' be applie'd to the data. EXAMPLE: 2588 cpm. ("K1") divided by .0531 vCf, (source activity)
= 48.738 cpm /pCi 48,738 cpm /pCi x .74 = 36,066 cpm /vci ,
1/36,066 = calibration constant 2.77 x 10-5 vCi/cp'm
. e The calibration constant is then ths reciprocal of the last 0 , corrected data. Record this value in space 3-3 on the 3rd Edit.
Data Sheet. {
- d. The beta particulate monitor (Ch.1). is a measufe of the beta activity on the filter paper. A plated source of 90S r 90y is the calibration standard. .The source is inserted into the i filter holder in place of the paper. After is printouts L (minimum), obtain the data from the last printtut and label the value *L." The value'"L" oivided by the activity of the source
- I equals the 2n efficiency. The 2n efficiency c.:ltiplied by 0.5 will give the 4n efficiency. The calibration constant is the
SPING 3/4 -
- CALIBRATION inverse of the result of the 43 sfficiency multiplied by 2.2 x e
100 (2.2 x 106 is the conversion factor from disinte-grations per minute to microcurie.). -
*The difference in backscatter factor between the source and a' .
filter paper must be considered in assigning source activity. Typically this difference causes the apparent source activity to increase about 25 percent. EXAMPLE : 1-7/S-inch (4.76 c[n) dia. active area 90 ,S r 90y , source, 1838 cpm 2 . Value "L" divided by 1838 cpm equals '23. efficiency
! 23 efficiency x 1/2 = 43 efficiency' 1 - Calibration Constant 4: Ef ficiency x 2.2 x 10 5 Record this value in space 1-3 on the 3rd Edit Data Sheet.
- e. At this point , determination of. the background subtration for the radon contribution must be made.
The alpha particulate channel (Ch.2)' monitors the same filter paper as the beta channel. Since radon daughters emit both alpha and beta particles, the decay of these daughts.s appears as beta particulate radiation. The effects of these radon
.. daughters' are nullified by measuring the radon alpha on the Channel 2 detector and subtracting a factored amount from the , *' beta channel. The following determines the factor.
Replace the calibration source with a clean filter paper.
. 1) ~
- 2) Turn on the pump.
- 3) Allow the pump to run for at' least two hours (minimum).
'~
- 4) Obtain the data from the last p'rintout of Channel 1 and
- label "M." . ,
- 5) Obtain the data from the last' printout of Channel 2 and
- label "H." .
- 6) A determination must be made at this point on the validity of the data. The data are valid only if no long lived particulates, such as fission products, are included in the data. Inclusion of such data in the determination of the factor will result'in over-subtraction ~ of radon back-ground. If there is no possibility of such particulates, prot' ecd to 6.e.8). below. ,
.SPING 3/4 , , CALIBRATION
- 7) . Shut off the sample flow. Wait for a minimum of 2 hours.
This allows the radon daughters to decay off by approxi-mately four half lives. The last printout of Channel If dataI should then be 0.062 or less of data "M" 6.e.4).
- are less, all contributions were from radon; proceed to ,
6.e.8),below. . Obtain the data "from the last printout and subtract from value "M." Label this result "M." This corrects the background determination for any long lived isotopes.
- 8) To determine the subtraction factor, data "M is divided by value "N". Record this value in space 1-4 on the 3rd Edit Data Sheet. ,
EXAMPLE: 0at,a after two hours running, Channel 1 = 200 cpm ("M") D'ata af ter tw'o hours running, Channel 2 = 100 cpm ("N") i Data after two' hours off, Cha'nnel 1 - 10 cpm
~
200 cpm ("M") divided by 100 cpm ("N") equals 2.00 x 100 Ekg. factor ,
- 7. ALARM SETPOINTS
- a. At this time, desired alarm set points shou'ld be edited into channel parameter files. The set point values are entered in fixed decimal point scientific notation. The trend alarm is ir.
percent / minute change. i
- 8. SAMPLE FLOW It is important to enter the sample flow rate into channels (1, 2, 3, 5, 7 and 9)'which depend upon sample flow for proper measurement.
Line 20 should be edited with the sample flow rate in cubic centi-meters per minute in their channel parameter files. If the unit uses the analog. input to measure sample flow r to the appropriate values Lines 19, 20, 21 and 22 should be edited', ate and/or stack f f for each flow dependent channel (1, 2, 3, 5, 7 and 9). See the l Analog Input Option manual section for further information. .
- a. Sample Flow Measurement f
The sample flow rate is indicated by the Photc'helicR gauge (FI) in liters per minute (lpn). Since this is not a " standard" or mass. independent measurement, the reading cn the instrument must be corrected for density altitude. The theoretical
o - SPING 3/4 - l CALIBRATION correction factor for the flowmeter is to multiply the reading by the s.quare root of the ratio of the operating absolute pressure to a standard atmosphere 14.7 psia (29.92 inches of Hg). Standard Flow = Observed Flow x.f operating absolute pressure Y 29.92 inches Hg
- ' where the operating absolute pressure is operating gauge pressure plus atmospheric pressure. As an' example, at an altitude of 4700 feet above sea level the atmospheric pressure is 12.37 psi (25.19 inches Hg). If the operating pressurc is 6 inches Hg vacuum as measured on the pump suction gauge (PI), The operating absolute pressure is -6 + 25.19 = 19.19 inches Hg. . Thus the correction factor would be ,~,. 0.80 g' 19.19 =
9 m
'- If the observed flow is 75 1pm, the corrected or standard flow is 75 1pm x 0.E0 = 60 1pm This is the value to be input as the sample flow rate in L.ine 20 , - of the flow-dependent channel's channel parameter file. Do not use the uncorrected PhotohelicR gauge reading.
- b. Sample F1'ow Adjustment
. It is important ;) keep the correction factor'in mind when adjus. ting the sample flow rate. In this case, knowing the ' - - standard . flow rate to be set and applying the correction factor !,, to yield indicated or observed flow allows'the.value to be set in by adjusting the flow rate. The flow' rate. is adjusted by mecns of the arjustment screw on the RAP-3 (regulated air pump) regalator. Th steps to set the flow rate ar.e as follows: . ~
a) Knowing the desired standard flow, divide by the I theoretical correction factor. , b) The calculated observed flow can then be set by adjusting
- the RAP-3 regulator until the PhotohelicR gauge indicates the observed flow rate. It may be helpful to read the RAP-3 and PhotohelicR flowmeter manual sections.
As an example: , It is desired to set the sample flow rate to 601pm. The pump pressure i,s 5.4 inches of Hg of vacuum and the 13-
. ~T~
SPI'NG 3/4 ,,
. cal.IBR ATION ,
barometric pressure is 24.5 inches of Hg. The observed flow rate is calculated to be: , , standard floit Observed flow = i[ operatina stancaro assolute atmospneric pressure pressure
= 60 lom
[-5.4 + 24.5 1 29.92
= 60 = 60 = 60 73J 19.1 , g0.64 1[29.92 = 75.1 ,
ThePAP-3ceghlatoristhenadjustedforanindicated (observed) flow of 75.1 1pm. 9.. Third Edit . Perform the third edit by entering all values from the 3rd Edit Data Sheet into the channel parameter files. A copy of.each edited < channel parameter file should be retained to aid in interpretation of . historical data. B. METHOD 2 . On-line calibration of the monitor may'be accomplished quickly and dynamically during operation by correlating laboratory data with SPItiG-3/4 data. At filter change time, the spent filter (or a gas sample) may be ar.alyzed
. in the laboratory for activity (or concentration). These data are then compared to the data from the SPItiG-3/4. Adjust,ments cah then be naa'd e to the calibration constant of the corresponding channel in the SPItiG-3/4.
This nethod is vaiid only if the laboratory methods of determination are more accurate than the SPIfiG-3/4. , Since the beta detector (Ch. I and 5) has a definite change in efficiency with dif ferent beta energies (isotopes), data. from the laboratory analysis C should include ' isotopic mix so this effect can be evaluated. { Any changes to the calibration constant which are greater that that which is deemed reasonable should.be cause for ' complete recalibration per Method - [
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. EPIP 1.3 MINOR Revision 0 - 03-31-81 o
ESTIMATION OF SOURCE TERM
. s 1.0 GENERAL The purpose of this procedure is to estiinate the source term (stack release rate in Ci/second) using the low range operational stack monitors, the Eberline RMS II Radiation Monitoring Systems or direct contict radiation measurements on the plant effluent vents. The plant effluent vent stacks are:
1.1 Auxiliary Building Vent (ABVNT) 1.2 Drumming Area Vent (DAVNT) 1.3 Unit 1 Containment Purge Vent (CONT 1) 1.4 Unit 2 Containment Purge Vent (CONT 2) 1.5 Gas Stripper Building Vent (GSBVNT) 1.6 Combined Air Ejector Decay Duct (CAE) 1.7 Main Steam Safety Valves and Atmospheric Dump Valves 2.0 REFERENCE 2.1 EDS Report to Wisconsin Electric Power Company concerning NUREG-0578, March 7, 1980. 3.0 PRECAUTIONS 3.1 If fuel damage or loss of reactor coolant system integrity has occurred, some or all of the following would be present: ( 3.1.1 The letdown radiation monitor (R9) may be unusually high or offscale. 3.1.2 The containment radiation monitors (R11 and R12) may be unusually high or offscale. l 1 i 3.1.3 The containment area monitors (R2 and R7) may be unusually high or offscale. l 3.1.4 The charging pump area monitor (R4) may be unusually high or ~ offscale. l (' . ma -r
a... . . . . . . . . . . . _ . . . . . _ . . . . . . . . , . .. ' EPIP 1.3 Page 2 1 3:2 Health Physics procedures and requirements must be followed when applicable (i.e., entering a high radiation area). l 3.3 Evaluation of the radiation monitoring system readouts and ramio-I' logical hazards must be completed prior to any attempt to enter the I auxiliary building or facade to take a contact reading on any stack. 4.0', INITIAL CONDITIONS 4.1 Applicable portions of EPIP 1.2, "P~ ant Status", is completed. 5.0 TROCEDURE FOR Xe-133 EQUIVALENT RELEASE RATE ESTIMATE - WORKSHEET NO. 1 5.1 Cheinistry/ Health Physics Supervisor or Designated Alt.rnate 5.1.1 Obtain EPIP-05 and EPIP-06 of EPIP 1.2, " Plant Status," for the radiation monitoring syrtems. NOTE: IF EPIP-05 AND EPIP-06 IN EPIP 1.2, "FLANT STATUS," ARE NOT COMPLETED, OBTAIN THE METER ; READINGS FOR EACH PLANT EFFLUENT VENT STACK FROM THE REMOTE' CONTROL ROOM READOUT AND RECORD THIS ON WORKSHEET i.0. 1 AMD THEN PROCEED WITH STEP 5.1.3. 5.1.2 Enter the meter readings and' flow rates in the appropriate colanns on Worksheet No.1 for the indica ted vents. If the readings are offscale, not monitored, or the monitors are inoperable, enter the appropriate word "offscale," "not monitored," cr " inoperable" in the meter reading column for the vent affected. 5.1.3 Designate individuals in accordance with ALARA concepts to obtain meter readings of the vents whose Eberline RMS II data is not available and the main steam header by performing Section 5.2 of this procedure if required. NOTE: IF STEP 5.1.3 NEEDS TO BE COMPLETED BECAUSE EBERLINE RMS II DATA IS NOT AVAILABLE, OR IF A STEAM GENERATOR TUBE RUPTURE IS BELIEVED TO HAVE OCCURRED WHICH PRODUCES THE POTENTIAL FOR RELEASES, OR RELEASES ARE IN PROGRESS FROM THE MAIN STEAM HEALER OR THE ATMOSPHERIC STEAM DUMP, THEN PERFORM SECTION 5.3 0F THIS PROCEDURE AFTER APPROPRIATE MEASUREMENTS HAVE BEEN TAKEN IN SECTION 5.2. 5,.l.4 Perform Section 5.3 of this procedure to determine the gross Xe-133 equivalent release rate estimcte.
# 4
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s EPIP 1.3 Page 3 Direct Stack Survey Team Designees
- [ 5 .'2 ,
NOTE: THE F LLOWING SECTION WILL NOT BE INITIATED UNTIL THE , EVALUATION DISCUSSED IN PRECAUTION 3.3 MAS BEEN COMPLETED AND THE SITE MANAGER (DUTY & CALL SUPERINTENDENT), THE DUTY & CALL HEALTH PHYSICS SUPERVISOR, AND THE DUTY SHIFT SUPERVISOR HAVE APPROVED INITIATION. THIS SECTION WILL BE ACCOMPLISHED UNDER THE DIRECTION OF HEALTH PHYSICS SUPERVISION. 5.2.1 Determine the most direct and cesirable route to the plant effluent stack to be monitored. 5.2.2 Determine the Health Physics requirements to be met for the passage to the vent areas. " 5.2.3 Determine the appropriate survey instcument to be used fo,r the plant effluent vent to be monitored. 5.2.4 Proceed by the route determined in Step 5.2.1 to the stack and *acord the survey instrument reading in contact with the stack in the columns provided on Worksheet No. 1, Part C, ' Plant Effluent Vent Stack Contact Readings. NOTE: IN THE CASE OF THE MAIN STEAM SAFETY VALVES AND ATMOSPHERIC STEAM DUMP VALVES, THE READING WILL BE TAKEN IN CONTACT k:IH THE CENTERLINE OF THE MAIN STEAM HEADER, THREE FEET FROM THE MAIN STEAM LINE. SHIELD THE PROBE (WITh A MINIMUM OF .25 INCHES OF LEAD) ON THE SIDES FACING THE MA~N STEAM LINE AND THE CONTAINMENT. 5.3 Chemistry / Health Physics Supervisor or Designated Alternate 5.3.1 Choose the appropriate vent stack readouts in Part A, B, or C cf Worksheet No. I to convert readings to a Xe-133 L l . equivalent release rate. That is if the low range monitors go offscale, use the high range monitor _. Conversely, if ( the normal monitors are enscale, use the normal monitors, or l if both normal and high range monitors are offscale or inoperable, use the vent stack contact readings. . 5.3.2 Use the appropriate attached conversion curves for each of l the plant effluent vent to convert the chosen vent stack l ' readout, (cpm or R/ hour) and flow rate, from Step 5.3.1 to l an Xe-133 equivalent release rate in Curies /second and l record the value on Worksheet No. 1, Part D, Estimate of ! Gross Xe-133 Equivalent Release Rate. Enter the appropriate word "offscale," "not monitored " or " inoperable" for the cases where the plant effluent vent was not monitored, offscale, or inoperable. f
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4 EPIP 1.3 Page 4 1 NOTE: THE FOLLOWING QUALIFYING NOTES MUST BE RECOGNIZED.
- 1. If the actual flow rate is different than the conversion curves flow rate, a ratio of:
Actual Flow Rate Conversion Curve FloJ Rate
' should be applied to determine the release rate.
(Ratio) X Conversion Curve = Adjusted Xe-133 Release Rate = Equiv. Release Rate
- 2. If the main steam header vent release rate needs to be deternined, the following steps must be
- applied.
- a. Obtain from the Shift Supervisor an estimated flow rate through the main steam header in ibm / hour of steam being dumped to the environ-ment and the specific volume (v) of the steam.
At 1000 psia, specific volume is 0.4.5 ft.8/lbm. At 500 psia, specific volume is 0.928 ft.8/lbm.
# UEL-Ibm /hr x v lbm~ x 7.86 ft.3 sec.
- b. Convert contact reading obtained at the main steam header to pCi/cc using the appropriate attached conversion curve for the main steam header.
pCi/cc
- c. Multiply flow rate obtained in Step (a) by the concentration obtained in Step (b) to obtain -
the release rate (Xe-133 equivalent) from the main steam header.
.F3ow Rate Concentration , Main Steam Header (cc/sec.) X (pCi/cc) Release Rate 5.3.2' Sum the values (1) through (7) on Worksheet No. 1, Part D, to determine the gross Xe-133 equivalent release rate.
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4 EPIP 1.3 Page 5 s. NOTE: IF GRAB SAMPLE RESULTS ARE AVAILABL8, THE RESULT OF SUCH SAMPLES SHOULD BE MORE ACCURATE THAN GROSS MONITOR READINGS AND HENCE Sh0ULD BE USED IN LIEU OF THE RELEASE RATES CALCULATED ABOVE OR IN ADDITION TO THE ABOVE IF THE RELEASE IS FROM AN UNMONITORED RELEASE PATH.
, 5.3.3 Report the calculated gross Xe-133 equivalent release rate
- to the Shif t Supervisor and the Technical Support Manager.
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. WORKSHEET No. 1 Xe-133 EQUIVALENT RELEASE RATE A. LOW RANGE OPERATIONAL VENT STACK READOUTS -
Meter Reading Flow Rate Conversion Curve
' Vent * (cpm) (cfm) Attachment No.
Auxiliary Building 51400 1.3-1 Drumming Area 43100 1.3-2 Unit 1 Containment Purge 12500/25000 1.3-3 and 1.3-4 Unit 2 Containment Purge 12500/25000 1.3-5 and 1.3-6 Gas Stripper Building 13000 1.3-7 Combined Air Zjector Decay 1.3-8 l B. EBERLINE RMS - II VENT STACK READOUTS l l Meter Reading Flow Rate Conversion Curve Vent (R/ hour) (cfm) Attachment No. Auxiliary Building 61400 1.3-9 Drumming Area 43100 1.3-10 Unit 1 Containment Purge 12500/25000 1.3-11 and 1.3-12 Unit 2 Containment Purge 12500/25000 1.3-11 and 1.3-12 Gas Stripper Building 1.3-13 Combined Air Ejector Decay 1.3-14 su - _ . . . - .__.____ax.-___ _ . - _ _ _ _ - - - . - _ .
- ~
r-- .
%, d ; C. PLANT EFFLUENT VENT STACK CONTACT READINGS ' Meter Reading Flow Rate Conversion Curve Vent (mr/hr or R/hr) (cfm) Attachment No.
Auxiliary Building 61400 1.3-15 Drumming Area 43100 1.3-16 Unit'l Containment Purge 12500/25000 1.3-17 and 1.3-18 Unit 2 Containment Purge 12500/25000 1.3-17 and 1.3-18 Gas Stripper Building 13000 1.3-19 Combined Air Ejector Decay 1.3-20 Main Steam Header 1.3-21 D. ESTIMATE OF GROSS Xe-133 EQUIVALENT RELEASE RATE , i Xe-133 Equivalent Release Rate Vent (Curies /Sec.)
- 1. Auxiliary Building
- 2. Drumming Area
- 3. Unit 1 Containment Purge
- 4. L* nit 2 Containment Purge
- 5. Gas Stripper Building
- 6. Combined Air Ejector Decay Duct
- 7. Main Steam Header
- 8. Sum (Gross Xe-133 Equiv. Release Rate)
QR .
- 9. Grab Sample Results = Ci/sec.
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