ML17193B502
| ML17193B502 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 06/23/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| TASK-06-07.A3, TASK-07-02, TASK-6-7.A3, TASK-7-2, TASK-RR LSO5-81-06-101, LSO5-81-6-101, NUDOCS 8106290447 | |
| Download: ML17193B502 (6) | |
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Docket No. 50-237 LS05 06-101 Mr. J. S. Abel
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t Director of Nuclear L1cens1ng Cominonwealth Edison Company Post Office Box 76:~
Chicago, Illinois 60690
- De~ r Mr. Abe}:
SUBJECT:
SEP TOPJC~ VI-7.A.3, ECCS ACTlJAXlON SYSTEMS AND VII-2, ENGJN~ERED SAFm FEATURES SYSTEtf'CONTROL LOGIC AND DESIGN. SAFETY EVALUATION REPORTS FOR DRESDEN 2 NUCLEAR POWER PLANT
~
The enclosed staff safety eval uat1ons are based on contractor documents that have been m~~~ available to.you previously. These evaluations are
.the staff's position regarding design of your facility in the subject areas. With regard to the referenced topics, the staff has concluded your facility *meets current 1 icensing criteria.
Enclosure:
As stated *
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- 8106290,_,Lf 7 Sincerely.
O~nn1s M~ Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing *
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- UNITED STATES NUCLEAR REGULATORY COMMISSION Docket No. 50-237 LSOS-81-06-101 Mr. J. S. Abel Director of Nuclear Licensing Commonwealth Edison Company.
Post Office Box 767.
Chicago, Illinois 60690
Dear Mr. Abel:
WASHINGTON, D. C. 20555 June 23, 1981
SUBJECT:
SEP TOPICS VI-7.A.3, ECCS ACTUATION SYSTEMS AND VII~2.
ENGINEERED SAFETY FEATURES SYSTEM CONTROL LOGIC AND DESIGN, SAFETY EVALUATION REPORTS FOR DRESDEN 2 NUCLEAR POWER PLANT The enclosed staff safety evaluations are based on contractor documents that have been made a~ailable to you previously~* These evaluations are
- the staff*s position regarding design of your facility in the subject a re as.
With reg a rd to the referenced to pi cs,. the staff has cone l uded your facility meets current licensing criteria.
Enclosure:
As stated cc w/enclosure:
See.next page Si nee rely,
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Mt~-;~L~~*
Dennis I. Crut'Chfield, ct1'i;f Operating Reactors Branch No. 5 Division of Licensing
. Mr. J. S. Abel cc Isham, Lincoln & Beale Counselors at Law One First ~ational Plaza, 42nd Floor Chicago, Illinois 60603 Mr. B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Ill{nois 60450 Natural Reso*urces Defense Council 917 15th Street, N. w.
Washington, D~ c.
20005
- 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 Morris Public Library 604 Liberty Street Morris, Illinois 60451 Chairman Board of Supervisors of.
Grundy County Grundy County Courthouse Morris, Illinois 60450 John F. Wolfe, Esquire 3409 Shepherd Street. __
Chevy Chase, Maryland 20015 Dr. Linda w. Little 500 Hermitage Drive Raleigh, North Carolina 27612
- 1 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:
EIS COORDINATOR 230 South Dearborn Street Chicago, Illinois 60604 Dr. Forrest J. Remick 304 East Hamilton Avenue Chicago, Illinois 60604
TOPIC:
VI-7.A.3 ECCS ACTUATION SYSTEM I.
INTRODUCTION The ECCS actuation system was reviewed with respecf to the testability of operability and performance of individual active components of the system and of the entire system as a whole under conditions as close to the design condition as practical.* The purpose of the reviews was to assure that all ECCS components (e.g., valves and pumps) are included
- in the component and system test and to assure that the scope of the periodic testing is adequate and meets the requirements of GDC 37.
The technical specifications were also audited for large differences between the present test requirements and those in the Standard Technical Specifica-
-ticins.
- I I.
REVIEW CRITERIA The current licensing criteria are identified in Section 2 of Lawrence Livermore Laboratory Report UCID-18698, Volume I, 11Systematic Evaluation Program Review of NRC Safety Topic VI-7.A.3 Associated w.ith the Electrical
. Instrumentation and Control Portions of the ECCS Actuation System for the Dresden II Nuclear Power Plant.
11 III. RELATED SAFETY TOPICS AND INTERFACES The related safety topics are identified in Appendix A to Report UCID-18698, Volume I. Only Topic VI-10.A is dependent on the present topic information for completion.
Response time testing is addressed in Topic VI-10.A.
IV.
REVIEW GUIDELINES The review guidelines are presented in Section 3 of Report UCID-18698, Volume I.
V..
EVALUATION Report UCID 18698, Volume.I describes the extent to which the ECCS actuation system can be tested, except for the question of response time testing.
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VI.
- CON CL US ION Based upon our review of our contractor's evaluation, the staff concludes that the Dresden 2 plant conforms to current licensing criteria and is, therefor~, acceptable.
-~.
I
,.-i TOPIC:
VlI-2 rnGrnEER. SAFETY FEATURES ( ESF) SYSTEM lnROL LOGIC AND DESIGN I.
INTRODUCTION During the staff review of the Safety Injection.System (SIS) reset (issue
- 4 in NUREG-0138) the staff determined that the Engineered Safety Features Actuation Systems (ESFAS) at both PWRs and BHR~ may have design features that raise questions about the independence of redundant channels, the interaction of reset features and individual equipment controls, a~d the interaction of the ESFAS logic that controls transfers between on-site and off-site power sources.
Review of the as-built logic diagrams and schematics, 6perator action required to supplement the ESFAS automatic actions, the*startup and surveillance testing procedures for demonstrating ESFAS performan~e appeared to be required.
Several specific concerns exist with regard to the manual SIS reset feat-ure following a LOCA.
They are:
(1) If a loss of offsite power occurs after reset, operator action would be required to remove normal.shutdown cooling loads from the emergency bus and re-establish emergency cooling loads.
Time would be critical if the loss of offsite power occurred within a few minutes followi~g a LOCA.
(2). If loss of offsite power*oc-.
curs after reset, some plants may not restart some essential loads such as rliesel cooling water.
(3) The plant may suffer a loss of ECCS delivery for some time period before emergency power picks up the ECCS system. It was also decided to review the ESF system control logic and design, in-cluding bypasses, reset features and interactions with transfers between onsite and offsite power sour~es.
Since these decisions were made in ~arly 1977, the staff's plans for re-solving these issues have changed.
Two generic reviews of the diesel generator problems have been conducted by Inspection and Enforcement.
The secorid review includes consideration of bypas~es and rese~s. In ad-di'tion, Task'Action Plan Generic Task 8-24 is involved with reset and by-pass concerns.
Accordingly, this SEP Topic has to be modified to reduce duplication of effort.
As a result of the staff's review of the scope of the. several related generic efforts and the other SEP Topics, it was decided that the only area that had not been cov*ered was the independence of redundant logic trains.
Independence might be compromised by sharing input sig~als and the use of common controls such as mode switches~* reset switches, and logic test facilities.
II.
REVIEW CRITERIA The c0rrent licensing criteria are presented in Section 2 of Lawrence Livermore Laboratory Report UCID 18698, Volume III, "Systematic Evalua-tion Program Review of NRC Safety Topic VII-2 Associated with the Electrical, Instrumentation and Control Portions of the ESF System Control Logic and Design for Dresden Station, Unit II Nuclear PovJer Plant."
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-- II I. RELATED SAFETY TOPICS AND IfHERFACES The scope of review for this topic v1as liiiiited to avoid duplication of effort since some aspects of the review were performed under related topics.
The related topics and the subject matter are identified below.
Each of the related topic reports contain the acceptance criteria and review guidance for its subj~ct matter.
III-6 III-11
- .III-12 IV-1.A VI-4.
\\II-7.A.3 VI-:- 7. B VI-7.C. l VI-7.C.2 VJ.-7.C.3 VI-7.D VI-7.F VI-10.A VI-10.B VII-1.A VII-3 VIII-2 ViII-3 VIII-4 I X-3 I X-6 Seismic Qualification Seismic Qualification Environmental Qualification Operation with Less than All Loops in Operation Bypass and Reset of Engineered Safety Features (B-24)
ECCS Actuation System ESF Switchover from Injection to Recirculation Independence of Onsite Power Failure Mode Analysis-ECCS The effect of loop isolation valve closure on ECCS performance Long Term Cooling Passive Failur~*(e.g. flo*oding)
Accumulator Isolation Valves Testing of Reactor Protection Systems Shared Systems Reactor Trip System Isolation Systems Requi~ed for Safe Shutdbwn Onsite Emergency Power Systems Emergency de Power Systems Electrical Penetrations Ventilation Fire Protection The coriclusion that suitable isolation devices are provided is a basic assumption for Topics VI-7.C.2 and VII~3.
IV.
REVIEW GUIDELINES The ~eview guidelines are presented in Section 3 of Report UCID 18698,
. Volume III.
\\I.
EVALUATION A description of the iso_lation devices employed in Dresd_en 2 and a compari-son with current design criteria are presented in Report* UCID 18698, Volume III.
VI.
CONCLUSION As a result of our review of our contractor's work the staff concludes that Dresden 2 conforms to current licensing criteria for electrical isolation of redundant safety features.