ML17244A494

Forwards Topics Deleted from Systematic Evaluation Program Review of Facilities.Requests Review & Identification of Errors within 30 Days from Receipt of Ltr

ML17244A494
Person / Time
Site:	Ginna
Issue date:	04/16/1979
From:	Ziemann D Office of Nuclear Reactor Regulation
To:	White L ROCHESTER GAS & ELECTRIC CORP.
References
TASK-***, TASK-05-01, TASK-05-03, TASK-05-07, TASK-05-08, TASK-05-13, TASK-06-02.B, TASK-07-01.B, TASK-07-04, TASK-07-05, TASK-07-06, TASK-08-01.A, TASK-09-06, TASK-11-01, TASK-11-02, TASK-13-02, TASK-15-22, TASK-15-23, TASK-RR NUDOCS 7905090026
Download: ML17244A494 (8)

Text

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Docket No. 50-244 Enclosure 2 is a list of topics that have been deleted from the review of

. your plant because they are not applicable to your facility or site.

Please review and identify any errors in these lists-and provide your comments within 30 days of the date you receive this letter. If no response is received within that time, we will assuage that you have no comments or corrections.

DISTRIBUTION oc e

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RVollmer TJCarter Nr. Leon D. White, Jr.

WRussell VicePresident'ELD Electric and Steam Production OI8E (3)

Rochester Gas and Electric Corporation DLZiemann 89 East Avenue JJShea Rochester, thew York 14649 HSmith DKDavis

Dear Nr. White:

JRBuchanan I

TERA This letter is to advise you of topics which have been deleted from the Systematic Evaluation'rogram (SEP) review of your facility.

Enclosure 1

is a list of topics being deleted because.

the same safety issues are being

-'eviewed as part of ongoing generic issues.

As indicated at the onset of the SEP many generic, issues would not. be evaluated. in the SEP;

however, the staff will consider any criteria resulting from the completion of the evaluation of a generic issue prior to the integrated assessment of your facility.

Sincerely,

Enclosures:

As Stated Oriyslal siC>ca o4e'nrlis L. Ziemann, Chief Operating Reactors Branch P2 Division of Operati'ng Reactors cc w/enclosures:

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Hr. Leon D. White, Jr. cc w/enclosures:

Lex K. Larson, Esquire

LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N.

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Washington, D.. C.

20036 Mr. Michael Slade 1250 Crown Point Drive

Webster, New York 14580 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.

P. 0.

Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza

Albany, New York 12223 Director, Technical Development Programs State of Hew York Energy Office Agency Building 2

.Empire State Plaza

Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 146P4 KM C, Inc.

ATTN:

Jack McEwen 1747 Pennsylvania

Avenue, N.

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Suite 1050 Washington, D.

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20006

E CLOSURE 1

R.

E.

GINNA SEP TOPICS NOT RE(UIRING REVIEW DUE TO ONGOING GENERIC LICENSING ACTIVITIES TOPIC V-1:

COMMENTS:

TOPIC V-3:

COMMENTS:

TOPIC V-7:

COMMENTS:

TOPIC V-8:

COMMENTS:

TOPIC V-13:

COMMENTS:

TOPIC VI-2-B:

COMMENTS:

COMPLIANCE WITH CODES AND STANDARDS The Engineering

Branch, DOR, is performing a review of all plants for compliance with inspection require-ments of 10 CFR 50.55a(g).

OVERPRESSURE PROTECTION Listed as TASK A-26 in NUREG-0371, "TASK ACTION PLANS.

FOR GENERIC ACTIVITIES", Published date November 1978.

Generic letters issued to PWR facilities in August 1976.

Specific criteria has been identified to be used in the design of modifications intended to preclude exceeding the limits of 10 CFR 50, Appendix G.

REACTOR COOLANT PUMP OVERSPEED Listed as TASK B-68 in NUREG-0371, dated November 1978.

At this time no criteria has been developed for this task.

STEAM GENERATOR INTEGRITY Listed as TASK A-3, 4, 5 of NUREG-0317, dated November 1978.

The TASK ACTION PLAN completely envelopes the scope of this topic review.

WATER HAMMER Listed as TASK A-1 in NUREG-0371, "TASK ACTION PLANS FOR GENERIC ACTIVITIES", Published date November 1978.

Generic letters sent to this facility May 1975.

SUBCOMPARTMENT ANALYSIS Listed as TASK A-2 in NUREG-0371, "TASK ACTION PLANS FOR GENERIC ACTIVITIES", Published dated November 1978.

Guidance letters issued to PWR licensees October 1975.

April 16, 1979

R.

E.

GINNA TOPIC VII-1-8:

COMMENTS:

TOPIC VII-4:

COMMENTS'OPIC VII-5:

COMMENTS:

TOPIC VII-6:

COMMENTS:

TRIP UNCERTAINTY 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.

FAILURES OF NON-SAFETY SYSTEMS AND SELECTED ESF'S The scope of this topic is contained in TASK A-17 of NUREG-0371, November 1978.

The staff is developing a method of review.

Criteria has not been established for implementation.

INSTRUMENTS FOR MONITORING ACCIDENTS TASK A-34 of NUREG-0371, November 1978.

Criteria under development.

FREQUENCY DECAY The scope of this topic is completely addressed in TASK A-35 (2.C-10) of NUREG-0371, November 1978.

TOPIC VIII-1-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-0371, November 1978.

Initial letters sent to l.icensee August 1976.

R.

E..GINNA 3

TOPIC IX-6:

COMMENTS:

TOPIC XI-1:

COMMENTS:

TOPIC XI-2:

COMMENTS:

TOPIC XIII-2:

COMMENTS:

TOPIC XV-22:

COMHENTS:

TOPIC XV-23:

COMMENTS:

FIRE PROTECTION This topic is being reviewed outside the SEPB as part of the ongoing licensing review implemented as a result of the Browns Ferry incident.

APPENDIX I This topic is part of an ongoing licensing review for all facilities to implement the limits of the Appendix I to 10 CFR 50.

RADIOLOGICAL MONITORING SYSTEMS

.Listed in NUREG-0371, November 1978, as TASK B-67, criteria and scope of review under development.

SAFEGUARDS/INDUSTRIAL SECURITY Ongoing licensing review to implement the require-ments of 10 CFR 73.55.

ANTICIPATED TRANSIENTS MITMOUT SCRAM TASK A-9 of NUREG-0371, November 1978, criteria for impl ementation under development.

STEAM.GENERATOR MULTIPLE TUBE FAILURES This topic is being considered in conjunction with TASK A-2, 3, 4 of NUREG-0371.

No criteria has been established on this topic.

~

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CLOSURE 2

R.

E.

GINNA SEP. TOPICS NOT APPLICABLE TO R.

E.

GINNA TOPIC NO.

II-4-E III-10-C IV-3 V-2

'ITLE Dam Integrity Surveillance Requirements on BWR Recirculation Pumps BWR Jet Pump Operating Indications Applicability of Code Case COMMENTS N/A to this unit site N/A BWR Safety Topic N/A BWR Safety Topic N/A at this time.

To be reviewed for any future modifications using references to Code Cases.

'V-9 Reactor Core Isolation Cooling System N/A BWR Safety Topic V-12.A VI-2.A VI-2-C Ice Condenser Containment N/A to this unit containment 'design Water Purity of BWR Primary Coolant N/A BWR Safety Topic Pressure Suppression'WR Containments N/A BWR Safety Topic VI-7-A-4 VI-7.D VI-9-A VI-10-B VII-7 XV-11 XV-13 Group I (BWR)

DBE Group VI DBE Core Spray Nozzle Effectiveness Long Term Cooling Passives Failures Main Steam Line Isolation Seal System Shared Engineer Safety Features Acceptability of Swing Bus Design on BWR-4 Plants Fuel Assembly Misloading Rod Drop Accident (BWR)

All Topic XV-13 (only)

Uncontrol led Rod Assembly Withdrawal at Power, Low Power Startup, Rod Drop Accident N/A BWR Safety Topic N/A No current cr',teria N/A BWR Safety Topic N/A to this unit site N/A BWR Safety Topic Review. on a routine basis as part of reload N/A BWR Safety Topic N/A BWR DBE Re'view N/A BWR DBE Review