ML17193B527
| ML17193B527 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/03/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| TASK-06-10.A, TASK-6-10.A, TASK-RR LSO5-81-07-004, LSO5-81-7-4, NUDOCS 8107130447 | |
| Download: ML17193B527 (3) | |
Text
Do~',
k.et. No. 50*2_fl
- LS
~81-07-004,.
- a.
Mr. J. S. "Abel Di rect_or of Nuc 1 ear L f cens fn*g Corrunonwealth E~ison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Abel:
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July 3, 1981
SUBJECT:
SEP TOPIC VI-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME, SAFETY EVALUATION REPORT (DRESDEN 2 NUCLEAR POWER PLANT)
The enclosed staff sa.fety evaluation is based on a contractor document that has been made available to you previously. This evaluation supports the find.ings of the staff safety evaluation of Topic VI-10.A and proposes
- modfffcat1ons to the Technical Spec1fi cations and some equipment to implement a response time testing progr.am. *
- The need to actually implement these changes wil 1 be determined during the integrated safety assessment. This topic assessment may be revised in th~ future if. your facility design is changed or if NRC criteria relating to this topic are modified before the integrated assessment
- 1 s completed.
Enclosure:
As stated cc w/enclosure:
See next page Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Bfanch #5
. Division of Licensing
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. Mr. J
- s...\\be l cc Isham, Lincoln & Beale Counsel ors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr. s. s. stepqi::ns~cin:
Plant Superi ntehdent Dresden Nuclear P6wer Station.
Rural Route #1 Morris, Illinois
917 15th Street, N. w.
Washington, D. c.
20005
~\\J. S. Nuclear Regulatory. Corrrnission Resident Inspectors Office Dresden Station RR #1.
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, i.orr1 s,. I 11 i noi s 60450 Mary Jo Murray Assistant Attorney General
-~nvircn~~ntal tontrol Division 1S8 w. Randolph Street Suite 2315 Ch~cc.i;o, Illinois 60601
'.-':or r i s P u b 1 i c l i bra ry 604 liberty Street Mo~ris, Illinois 60451 Chairman Board of Supervisors**of Grunc;iy County Grundy" County Courthouse Morris, Illinois 60450 John F. Wolfe, Esquire 3409 Shepherd Street Chevy Chase, Maryl and 20015 Dr. *Linda-w. Little 500 Hermitage Drive Raleigh, North Carolina 27612
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DRESDEN.2
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Docket No. 50-237 *..
- Illinois Depart~~.tit :of Nuclear Safety 1035~ Outer Park;::Of*i ve, 5th Floor Spri*ngfie l d, Ll iV'Ooi s *
- 62704 *
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- U. ~~ Envir9nrrient41.Protection Agency F~e"ra 1 Acti vitfe~ Branch Regi o,n v Office ATIN:
EISCOORDINATOR 230 So~th Dearborn Street Chicago, Illinois; 60604
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- Dr.:~*.F6rrest J. Remick.
304 East Hamilton Av~nue.
- Chica.go, Illinois 60604
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- NCLOSURE..
TOPit; VI-10.A, TESTING OF ~EACTOR TRI~*SY~TEM AN6 ENGINEERED SAFETY FEATURES, INCLUDING ~ESPONSE TIME TESTING I.
INTRODUCTION.
The p~rpose of this T6pic is ta* ~e~iew the ~eactor trip system {RTS) and engineered*.safeti features (ESF) test program. for verification of RTS and ESF operability on a periodic basis and to verify RTS and ESF response ti me in order to assure the. operability of the RTS and ISF.
Response times should hot exceed those assumed in the. plant*
acci den_t analyses.
- Accardi ngly, the test program of the RTS and ESF was reviewed in ~ccordance with the Standard Review Plan, including applicable Branch Technical Positions.
II.
REVIEW CRITERIA The revi.ew criteria are presented in* Sec ti ori
- 2 of Lawrence Livermore Laboratory Report UCID 1889, Vol. II, "Systematic Evaluation Program Review of NRC Safety Topic VI-10.A Associated.with the Electrical, Instrumentation and Control Portions of the Testing of Reactor Trip System and Engineered Safety Features, Including Response Time for the Dresden Station, Unit 2 Nuclear Power Plant."
I IL RELATED SAFETY TOPICS AND INTERFACES Topic VI-7.A.3 discusses the question. of testing protection systems under conditions as close to design condition as practical. There are no topics that are dependent dn the present topic information for their completion.
IV, REVIEW GUIDELINES Review guidelines are presented.in Section 3 of Report UCID 18698, Vol. I I.
V.
EVALUATION Dresden 2 comnlies with the curr~nt licensing criteria, exc~pt for IIEE Std 338-1975, Section 6.3.4 (res~onse time testinq).
VI.
CONCLUSION It is the staff's position that*the design of systems which are required for. safety.shal 1 include provisions for periodic verification that the minimum performance of.instruments and control is not less than that which was assumed in the safety analyses. The bases for this position are General Design Criterion 21, Section 3.9 of IEEE Std *
. 279-1971, and IEEE Std. 338-1971.
Therefore, the licens~e should impl anent a program for response time t~sting of all reactor protection systems (incluqing engineered safety features systems such as containment isolation).
As a part of this.program, the response time test requi~ements should be state~ in the Technical Specifications in a manner similar to thaLof. the Standard Technica1 Specifications.*
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