ML17244A522
| ML17244A522 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/16/1979 |
| From: | White L ROCHESTER GAS & ELECTRIC CORP. |
| To: | Ziemunn D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7905220377 | |
| Download: ML17244A522 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR!7905220377 DOC ~ DATE:'9/05/16 NOTARIZED!
NO DOCKET FACIL!50 244 ROBERT EMMET GINNA NUCLEAR PLANTi UNIT ir ROCHESTER G.
05000244 AUTH,NAME AUTHOR AFFILIATION WHITE p L'e D ROCHESTER GAS L ELECTRIC CORP ~
RECIP ~NAME'ECIPIENT AFFILIATION Z IEMUNNi0 it" OPERATING REACTORS BRANCH 2-SUBJECT!
COMMENTS ON 790416 LTR DELETING TOPICS FOR FURTHER REVIEW FROM SYSTEMATIC EVALUATION PROGRAMS DISTRIBUTION CODE.:
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~ j/jiPjpyt/jgyipe~~tzrs ROCHESTER GAS AND ELECTRIC CORPORATION 89 EAST AVENUE, ROCHESTER, N.Y. 14649 PC ~
LEON D, WHITE, JR.
VICE PRESIPENT 7 C I. C P H0 H E ARCA CODE TIC 546.2700 May 16, 1979 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis L. Ziemann, Chief Operating Reactors Branch No.
2 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
SEP Topics R.E.
Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Ziemann:
We have reviewed your letter of April 16, 1979 which deleted a number of topics from further review in the Systematic Evaluation Program, and have several comments for your consideration.
1)
A number of generic topics were deleted inasmuch as they are subject to ongoing NRC review:
Topic V-3, Overpressure Protection, was one of these topics.
However, this topic should be listed as complete based on the NRC letter dated April 18, 1979.
The April 18 letter approved plant modifications and issued Technical Specifications for reactor vessel overpressure protection.
Topic V-7, Reactor Coolant Pump Overspeed, has also been deleted from SEP review.
- However, since Topic III-10.B, Reactor Coolant Pump Flywheel, is currently under review, and is closely related to Topic V-7, it is not clear how only one of these two topics can be deleted.
Topic V-13, Water
- Hammer, should be shown as being complete.
This is based on the installation of "J-tubes" on the Ginna steam generators and on administrative actions detailed in our letters of January 3 and June 15,
- 1978, "Steam Generator Water Hammer Prevention".
Topic XIII-2, Safeguards/Industrial
- Security, should be shown as complete.
The Staff Security Safety Evaluation Report, was issued as Amendment No.
25 to the Ginna license on February 22, 1979.
79058203 0@i 5
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~~N ROCHESTER GAS AND ELEC IC CORP.
May 16I 1979 To Director of Nuclear Reactor Regulation Attention:
Mr. Dennis L. Ziemann SHEET NO.
2)
Several SEP Topics were determined to be not applicable to Ginna.
Your letter indicates that Group I (BWR) DBE's are not applicable.
It is our understanding that this group includes part of one topic, XV-3:
Inadvertent Closure of MSIV's. It appears that a number of other topics should also be deleted because they are not applicable or because they have been resolved.
For example, topic XV-ll, Fuel Assembly Misloading, is deleted because it is reviewed on a routine basis as part of reload evaluations.
Many other design bases events are also reviewed as part of reload evaluations.
The following DBE's were reviewed in Exxon.
Topical Report XN-NF-77-40, dated
- November, 1977:
XV-2, Spectrum of Steam Line Breaks XV-3, Loss of External Load XV-7, RC Pump Motor Seizure XV-S, Control Rod Misoperation These analyzed DBE's generally envelope other transients whose con-sequences are known to be less severe.
These other transients are:
XV-4, Loss of AC Power XV-5, Loss of Normal Feedwater Flow XV-9, Startup of Inactive Loop XV-lO,CVCS Malfunction Reactivity XV-14,Inadvertent CVCS Malfunction Inventory Some or all of these nine transients can also be removed from the SEP topic list on the same basis as XV-11.
- 3) It is not clear on what basis Topic VI-7.D, "Long-Term Cooling Passive Failures", is being deleted.
The rationale used in the letter would indicate its placement into the ongoing generic topic category.
4)
The following topics should also be identified as completed:
Topic II-4.F, Settlement of Foundations and Buried Equipment, should be complete based on the lack of adverse effects of settlement in ten years of operation.
Topic III-3.C, ISI of Water Control Structures, should be deleted since Ginna has no water control structures.
Topic III-7.D, Containment Structural Integrity Test, is complete based on the testing of the Ginna containment which was performed in 1969.
Topic VI-7.A.1, ECCS Reevaluation to Account for Increased Vessel Head Temperature, is complete based on the NRC letter dated May 1, 1978.
1 ROCHESTER GAS AND ELEC IC CORP.
DATE May 16, 1979 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis L. Ziemann SHEET NO.
Topic V-7.C.3, Effect of PWR Loop Isolation Valve Closure During LOCA on ECCS Performance, should be deleted since Ginna does not have loop isolation valves.
We appreciate the opportunity to provide comments on the SEP topic resolutions.
Very truly yours,