ML17194B296
| ML17194B296 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/02/1982 |
| From: | Oconnor P Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| TASK-06-10.A, TASK-6-10.A, TASK-RR LSO5-82-09-018, LSO5-82-9-18, NUDOCS 8209140330 | |
| Download: ML17194B296 (5) | |
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7'j Docket No. 50-237 LSOS-82:..09-018 Mr. L. DelGeorge Director of Nuclear Licensing Co!lVTlonwealth Edison Company Best Office Box 767 Chicago, Illinois 60690
Dear Mr. DelGeorge:
September 2, 1982
SUBJECT:
SEP TOPIC VI-10.A, TESTING OF REACTBR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLVliHNG RESPONSE TIME TESTING, REVISED SAFETY EVALUATION REPORT FOR DRESDEN UNIT 2 NUCLEAR POWER STATION
.*The enclosei~ revised s~aff safety evaluation is based on a contractor
. document that has been made available to you previously, test procedure
- DSI 500-9, and our review of this topic for Palisades *
. As a result of our review, we find that your facility satisfies our requireii:lents (wit!i: the exception of response time testing of the sensors.
This safety evaluation* will be a basic input to the Integrated Safety Assessment for your facility *. This assessment may be revised in the future if your facility design is changed or ff NRC crit~ri~ relating
- to this subject are modified before the Integrated Assessment is*
completed.
Sincerely, I
Original signe*d by:
Encl<Dsure:
As stated Paul W. 0 'Connor, Project Manager sO '/
Operating Reactors Branch No *.. 5
(,)
Di vi sfon of L f censing
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cc w¢anclosure:
See 'next page 8209140330 820902 3
- PDR ADOCK 05000237 P
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- See. previous concurrence NRC FORM 318 (10-80) NACM 0240 OFFICIAL RECORD COPY USGPO: 1981-335-960
OFFICE.
SURNAME.
DATE.
Docket No. 50-237 LSOS-82 Mr. L. DelGeorge Director of NUclear Licensing Corrmonwealth Edison Company Post Office Box 767 Chicago. Illinois 60690
Dear Mr. DelGeorge:
SUBJECT:
SEP TOPIC VI-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES. INCLUDING RESPONSE TIME. REVISED SAFETY EVALUATION REPORT (DRESDEN 2 NUGL~AR POWER STATION)
The enclosed revised staff safety evaluation is based on a contractor document that has been made available_ to you previously, test procedure OSI 500-9. and our review of this topic for Palisades.
As a result of our review, we find that your facility satisfies our requirements and is, therefore, acceptable.
This safety evaluation will be ~ basic input to the integrated safety assessment for your *facHity. This assessment may be revised in the-future if your facility design is changed or if NRC criteria relating to this subject are modified before the integrated assessment is completed.
Enclosure:
As stated cc w/enclosure:
See next page
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SEPB:DL RHermann*
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Sincerely, Paul O'Connor, Project Manager Operating Reactors Branch No. 5 Division of Licensing SEPB:DL ORB#5:PM ORB#5;BC WRussell PO'Connor
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NRC FORM 318 (10-Bo) NRCM 0240 OFFICIAL RECORD COPY AD:SA:DL Glainas
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USGPO: 1981-335-960
"-~
r M~. L. DelGeorge cc Robert G. Fitzgibbons, Jr.
Isham, Lincoln & Beale Three First National Plaza Suite 5200 Chicago, Illinois 60602 Mr. Doug Scott Plant Superintendent Rural Route #1 Morris, Illinois 60450 e*
. u. s. Nuclear Regulatory Commission Resident Inspectors Office Dresden Station RR #1.
Morris, Illinois 60450 Mary Jo Murray Assistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 U. S. Environmental Protection Agency Federal Activities Branch Region V Office ATTN:
Regional Radiation Representative 230 South Dearborn Street Chicago, Illinois 60604 The Honorable Tom Corcoran United States House of Representatives Washington, D. C.
20515 John H. Frye, III, Chairman Atomic Safety and Licensing Board U. S. Nuclear Regulat1ry Commission*
Washington, D. C.
20555 Dr. Martin J. Steindler Argonne National Laboratory 9700 South Cass Avenue Argonne, Illinois 60439 Daniel Mintz, Esquire Counsel for Petitioners (Citizens for a Better Environment)
Suite 1600, 59 E. Van Buren Street Chicago, Illinois 60605 Dr. Robert L. Holton School of Oceanography Oregon State University Corvallis, Oregon 97331 James G. Keppler, Regional Administrator Nuclear Regulatory Commission, Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
SYSTEMATIC EVALUATION PROGRAM TOPIC VI.:.10.A DRESDEN 2 TOPIC:
VI-10.A, TESTING OF REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES, INCLUDING RESPONSE TIME TESTING I.
INTRODUCTION The purpose of this topic is to r.eview the reactor trip system (RTS) and engineered safety features (ESF) test program for verification of RTS and ESF operability on a periodic basis and to verify RTS and ESF response time in order to assure the operability of the RTS and ESF.
Response times should not exceed those assumed in the plant accident analyses.
Accordingly, the test program of the RTS and ESF was reviewed in accordance with the Standard Review Plan, including applicable Branch Technical Positions.
II.
REVIEW CRITERIA The review criteria are presented in Section 2 of Lawrence Livermore Laboratory Report UCID 1889, Volume 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.
III.
RELATED SAFETY TOPICS AND INTERFACES Topic Vl-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 on the present topic information for their completion.
IV.
REVIEW GUIDELINES Review guidelines are presented in Section 3 of Report UCID 18698, Volume II.
V.
. EVALUATION Report UCID 18698 notes that Dresden 2 complies ~ith the current licensing criteria, except for IEEE Std 338-1975, Section 6.3.4 (response time testing).
The staff's review of response time testing at Dresden 2 has shown that mechanical systems that provide the major time delays such as the control rod drive system, diesel generators and the major ECCS valves and pumps and containment isolation valves are response time tested.
In addition, test procedure DIS 500-9 is used to response time test the reactor protection system logic relays.
.J
...~ The sensors, however, are not tested. Based on the limited risk assessment that was done on Palt~ades it is the staff's opinion that response time changes i'n this type of instrumentation is a small contributor to core damage.
Therefore, the resnlutton of this item can be delayed until the Integrated Safety Assessment.
Vl.
CONCLUSION As a result of our review of ~he work of our contractor and our own review of response time testing, the*staff has concluded that Dresden 2 satisfies our review guidelines wtth the exception of response time testing of the sensors. This.issue wi"l 1 be addressed i'n the Integrated Safety* Assessment for Dresden 2.