ML17256A440
| ML17256A440 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/29/1982 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 GL-82-16, NUDOCS 8301040708 | |
| Download: ML17256A440 (6) | |
Text
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'ACCESSION NBR:8301040708 DOC ~ DATE: 82/1'2/29 NOTARI'ZED:
NO DOCKET
,.FACIL:50 244 Robert Emmet Ginna Nuclear:Pl anti Uni<<t 1i Rochester G
05000244 AUTH BYNAME AUTHOR AFFILIATION MAIERiJ ~ E ~
Rochester Gas 8 'Electric Corp>
'RECIP ~ NAME RECIPIENT AFFILIATION
'CRUTCHFIELDiD, Operating Reactors Branch
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SUBJECT:
Responds
~to 820920 Generic Ltr 82 16 re NUREG 0737 'items, of 13 items, 11 nest applicable or reviewed under other-<<topic submi ttal s, Item '2i,"Limi~t Overtime L Item 12i."Repor ting "Safety 8 Relief Val,ve Failures" 'implemented.
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IIlllll IllliZEPll 8Z; ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAILER Vice Predklent TCCCPHO>C ARCA CODC 7id 546-2700 L
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.December 29, 1982 II F
H Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
NUREG-0737 Technical Specifications (Generic Letter No. 82-16)
R. E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
Darrel Eisenhut's letter dated September 20, 1982 requested that we review our Technical Specifications to determine if they are consistent with guidance provided in his letter.
We have reviewed the letter and find that eleven of the thirteen items are either not applicable, have been previously included in Technical Specifications or are being reviewed under other specific topic submittals as follows.
Shift Technical Advisor requirements (item 1) have been included in our Technical Specifications beginning with Amendment 42 and are included in proposed changes to our organization chart submitted September 28, 1982.
Auxiliary feedwater system require-ments (items 3 and
- 4) are included in our Technical Specifications as specifically addressed in our letter dated June 6,
1981.
Dedicated hydrogen penetrations (item 5) and B&W auxiliary feed-water system requirements (item 9) are not applicable to the R. E.
Ginna plant.
The containment setpoint pressure (item 6) was revised in license Amendment 47.
Containment purge valve require-ments (item 7) are being addressed separately as part of the over-all containment purge review.
A requirement for a radiation signal to close the containment purge valves (item 8) was included in the Technical Specifications in license Amendment 47.
A thermal-mechanical report (item ll) was submitted as referenced in our January 19, 1982 letter.
No technical specification changes resulting from this report have been identified.
An anticipatory trip on turbine trip (item 13) was included in our Technical Specifications prior to the TMI event as given on Table 3.5-1.
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ROCHESTER GAS AND ELEC7RIC CORP.
oATE December 29, 1982 To Mr. Dennis M. Crutchfield SHEE7 NO.
2 The remaining two items, limit overtime (item 2) and reporting safety valve and relief valve failures and challenges (item 12) have been implemented but have not yet been included in our Technical Specifications.
A proposed amendment to incorporate these items is being prepared and should be reviewed and completed within the next two months.
Very truly yours,
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