ML19262A772
| ML19262A772 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/16/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Peoples D COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 7912110017 | |
| Download: ML19262A772 (8) | |
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o UNITED STATES NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D. C. 20555 g
November 16, 1979 g
Docket No. 50-10 Mr. D. Louis Peoples Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Peoples:
By letter dated April 16, 1979, we sent you the list of topics which would not be reviewed for your plant in the Systematic Evaluation Program (SEP).
These topics were proposed for deletion from the SEP because they were not applicable to your plant or they were being reviewed as part of an ongoing generic issue outside the SEP. Most of the licensees of plants in the SEP provided corrents on these lists. We have reviewed those conrants and have conducted further internal review of our original listings.
.o a result, we have enclosed new listings which supersede the lists transmitted on April 16, 1979. is the list of topics which are being reviewed as part of ongoing generic issues outside of the SEP. The SEP will only' monitor the status of hese topics.
If the topic is completed and implemented during the course of the SEP, a topic assessment will be issued which identifies the licensing action and safety evaluation report (SEP,) supporting the final disposition of that topic.
If an inplementation position is developed but no licensing action has been taken, the issue will be considered for implementation on SEP plants on a case-by-case basis.
If no implementation position has been developed by the end of the SEP, the topic assessment will merely report the status of the generic effort. is the list of topics that have been deleted from the review of your plant because they are not applicable to your facility or site. No topic assessnents will be written for these topics.
Sinc erely, W
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- \\ Dennis L. Ziem;nn, Chief Operating Reat. tors Branch #2 Division of Operating Reactors
Enclosures:
As stated 1532 292 cc w/ enclosures:
See next page h[
7912110
fir. D. Louis Peopl.es November 16, 1979 cc w/ enclosures:
Isham, Lincoln & Beale Counselors at' Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Mr.' B. B. Stephenson Plant Superintendent Dresden Nuclear Power Station' Rural Route #1 Me rri s,.. Il l inoi s 60450 U. S. Nuclear Regulatory Commission ATTN: Jimmy L. Barker P. 0. Box 706 Morris, Illinois 60450 Susan N. Sekuler Assistant Attorney General tineironmental Control Division 188 W. oandolph Street Suite 2315 Chicago, Illinois 60601 Morris Public Library 604 Liberty Street Morris, Illinois 60451 K M C, Inc.
ATTN: Richard E. Schaffstall 1747 Pennsylvania Avenue, N. W.
Saite 1050 Washington, D. C.
20006 1532 293
ENCLOSURE 1 DRESDEN 1 SEP TOPICS NOT REQUIRING REVIEW DUE TO ONG0ING GENE _RIC LICENSING ACTIVITIES TOPIC III-8.A:
LOOSE PARTS MONITORING AND CORE BARRELL VIBRATION MONITORING COMMENTS:
Implementation status pending RRRC decision.
TOPIC III-B.D:
CORE SUPPORTS AND FUEL INTEGRITY COMMENTS:
This topic is being reviewed generically by PWR under TAP A-2 for PWRs. Future A-2 under development for BWRs.
TOPIC III-9:
SUPPORT INTEGRITY COMMENTS:
Generically reviewed under TAP A-12.
TOPIC V-1:
COMPLIANCE WITH CODES AND STANDARDS COMMENTS:
The Engineering Branch, DOR, is performing a generic review of all plants for compliance with inspection reouirements of 10 CFR 50.55a(g).
TOPIC V-4:
PIPING AND SAFE END INTEGRITY COMMENTS:
Included in the review for 10 CFR 50.55a.
TOPIC V-13:
WATER HAMMER C0"MENTS:
Listed as TASK A-1 in NUREG-0371, " TASK ACTION PLANS FOR GENERIC ACTIVITIES", published dated November 1978.
Generic letter sent to PWR facilities, requirements; not established for SWRs.
TOPIC VI-2.B:
SUSCOMPARTMENT ANALYSIS COMMENTS:
Listed as TASK A-2 in NUREG-0371, TASK ACTION PLANS FOR GENERIC ACTIVITIES", published date November 1978.
Guidance letters issued to PWR licensees October 1975.
The staff is currently. developing plans for expanding this activity to resolve this issue for BWR facilities (NUREG-0510). Specific requirements and scope have not been established.
i532 294 November 16, 1979
. TOPIC VI-6:
CONTAINMENT LEAK TESTING COMMENTS:
Reviewed under TAP A-23.
TOPIC VI-7-D:
LONG TERM COOLING PASSIVE FAILURES COMMENTS:
Generically reviewed and determination as stated in NUREG-0138.
TOPIC VI-7-E:
Reviewed under TAP A-43.
TOPIC VI-7.A.4:
CORE SPRAY N0ZZLE EFFECTIVENESS COMMENTS:
Listed as TASK A-16 in NUREG-0371, " TASK ACTION PLANS FOR GENERIC ACTIVITIES", published date November 1978.
December 1976 - letter issued to licensee.
TOPIC VII-1.S:
TRIP UNCERTAINTY COMMENTS:
Staff evaluations, issued August 1978, state that review is being pursued independent of SEP to determine impact of instrument error and drift upon safety margins of trip setpoints, and that appropriate actions will be taken to assure that adequate safety margins are maintained.
TOPIC VII 4:
FAILURES OF NON-SAFETY SYSTEMS AND SELECTED ESFs COMMENTS:
The scope of this topic is contained in TASK A-17 of NUREG-0371, November 1975. The staff is developing a nethod of review. Criteria has not been established for implementation.
TOPIC VII-5:
INSTRUMENTS FOR MONITORING ACCIDENTS COMMENTS:
TASK A-34 of NUREG-0371, November 1978. Criteria under development.
TOPIC VII-6:
FREQUENCY DECAY COMMENTS:
The scope of this topic is completely addressed in TASK A-35 (2.C-10) of NUREG-0371, November 1978.
TOPIC VIII-l.A:
EFFECTS OF DEGRADED GRID VOLTAGE COMMENTS:
The scope of this topic is contained in TASK A-35 (C-2, 3, 4 and 5) of NUREG-C371, November 1975.
Initial letters sent to licensee August 1976.
1532 295
,T]PIC IX-2:
OVERHEAD HANDLING SYSTEMS - CRANES
.0MMENTS:
Reviewed under TAP A-36.
TOPIC IX-6:
FIRE PROTECTION C0ft1ENTS:
This topic is being reviewed outside the SEP as part of the ongoing licensing review implemented as a result of the Browns Ferry incident.
TOPIC XI-1:
APPENDIX I COMMENTS:
This topic is part of an ongoing licenseing review for all facilities to implement the limits of the Appendix I to 10 CFR 50.
TOPIC XI-2:
RADIOLOGICAL MONITORING SYSTEMS COMMENTS:
Listed in NUREG-0371, November 1978, as TASK B-67, criteria and scope of review under development.
TOPIC XIII-1:
CONDUCT OF OPERATIONS COMMENTS:
Generically reviewed by DPM with the exception of
" Operating Experience" which will be provided by I&E.
TOPIC XIII-2:
SAFEGUARDS / INDUSTRIAL SECURITY C0t41ENTS:
Ongoing licensing review to implement the requirements of 10 CFR 73.55.
TOPIC XV-21:
SPENT FUEL CASK DROP COMMENTS:
Reviewed under TAP A-35 TOPICXV-21 ANTICIFATED TRANSIENTS WITHOUT SCRAM COMMENTS:
TASK A-9 of NUREG-0371, November 1978, criteria for implementation under development.
TOPIC XV-24:
LOSS OF ALL AC POWER COMMENTS:
Reviewed under TAP A-44.
TOPIC XVII:
QA FOR OPERATIONS COMMENTS:
Reviewed by QAB for conformance with 10 CFR 50 Appendix B.
1532 296
ENCLOSURE 2 ORESDEN 1 SEP TOPICS NOT APPLICABLE TO DRESDEN 1 TOPIC NO.
TITLE COMMENTS III-3.B Failure of Underdrain System N/A to this unit design III-7.A Inservice Inspection, Including N/A Ho Current Criteria Prestressed Concrete Containments With Either Grouted or Ungrouted Tendons III-7.C Delamination of Prestressed Concrete N/A to this containment Containments design 111-10.B Pump Flywheel Integrit; N/A PWR Safety Topic III-10.C BWR. Recirculation and Discharge N/A to this facility Valve Surveillance design IV-3 BWR Jet Pump Operating Indications N/A to this reactor design V-2 Applicability of Code Cases N/A at this time. To be reviewed for any future modifications using references to Code Cases V-3 Overpressure Protection Safety issue N/A to BWRs on operating experience.
V-7 Reactor Coolant Pump Overspeed N/A PWR Safety Topic V-8 Steam Generator Integrity N/A to this unit. The steam generators at 01 do not serve as a pri-mary boundary.
V-9 Reactor Core Isolation Cooling N/A to this facility System (BWR) design VI-2.A BWR Pressure Suppression Containment N/A to this containment design VI-2.C Ice Condenser Containment N/A to this facility design VI-7.A.1 Increased Vessel Head Temperature N/A PWR Safety Topic VI-7.A.2 Upper Plenum Injection N/A PWR Safety Topic iSD 297
. TOPIC NO.
TITLE COMMENTS VI-7.B ESF Switchover from Injection to N/A - D1 takes suction Recirculation from the fire systera for injection, although the potential for failure to switchover exists, the consequences are not the same as the PWRs since the fire water system is considered to have an infinite water source and switchover to containment spray does not utilize the same equipment nor is the need to initiate spray the same as that of the PWRs.
VI-7.C.3 PWR Loop Isolation Valve' Closure N/A PWR Safety Topic VI-7.F ECCS Accumulator Design N/A PWR Safety Topic VII-7 Acceptability of Swing Bus Design N/A to this facility on BWR-4 Plants design IX-4 Boron Addition System (PWR)
N/A PWR Safety Topic X
Auxiliary Feedwater System N/A PWR Safety Topic XV-17 Steam Generator Tube Failure (PWR)
N/A to this unit - the steam generators at 01 do not serve as a pri-mary boundary.
XV-23 Steam Generator Multiple Tube N/A to this unit - the Failure steam ganerators at D1 do not serve as a pri-mary boundary.
Group I All N/A PWR DBE Review (PWR) DBE Group II Only Topic XV-6 Feedwater System N/A PWR DBE Review Pipe Break 1532 298 TOPIC NO.
TITLE COMMENTS Group III All N/A PWR DBE Review Group VI Only Topic XV-12 Spectrum of N/A PWR DBE Review Rod Ejection Accidents Group X All N/A PWR DBE Review 1532 299
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