ML20073E087
| ML20073E087 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/08/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM GL-83-02, GL-83-2, JPN-83-31, NUDOCS 8304140332 | |
| Download: ML20073E087 (5) | |
Text
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s POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMaus CIRCLE NEW YORK. N.Y. l oo19 (212) 397 6200 LEnov w siNCLA'a
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April 8, 1983
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.C OCHAmo M. FLYNN J1 MIS L LARoCC A STE. PHEN L.B AUM couANo E..uoorn Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactor Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Technical Specifications R3forences:
1.
NRC Generic letter 83-02, D.G.
Eisenhut to All BWR Licensees, dated January 10, 1983.
2.
PASNY letter, J.P.
Bayne to D.B. Vassallo, dated June 21, 1982 (JPN-82-53).
3.
PASNY letter,J.P. Bayne to D.B. Vassallo, dated February 8, 1982 (JPN-82-18).
Dear Sir:
Reference 1 requested that the Authority review the FitzPatrick Technical Specifications to determine if they are consistent with the guidance provided for NUREG-0737 items due to have been implemented by December 31, 1982.
The Authority has completed this task, and the results of the re-view are discussed in Attachment 1 to this letter.
Requests for changes to the Technical Specifications will be sent under separate cover.
If you require any further information, please contact Mr. J.A. Gray, Jr.
of my staff.
Very truly yours,
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_Mo (awn J.P. Bayn E f x cube Mce pesident F304140332 830400 Nuclear Generation PDR ADOCK 05000333 P
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l Resident Inspectdr t? S. Nuclear Regitlat'riry, Commission Post Of fice Box 136'..' i Lycoming, New York \\l3093
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.- FITZPATRICK NUCLEAR POWER PLANT ATTACHMENT 1 TO JPN-83-31 DATED April 8, 1983 y
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i to Generic Letter 83-02 provided guidance on a number of NUREG-0737 items which require Technical Specifications.
The following discussion uses the same numbering system as Enclosure 1.
(1)
STA Training (I.A.l.l.3)
This item is not addressed in this submittal pending further guidance' from the Commission as stated in the Generic Letter.
I (2)
Limit Overtime (I.A.l.3)
Plant Standing Order #26, " Overtime Policy'I, sets policy for the FitzPatrick Plant in this area, and is in keeping with NUREG-0737 requirements as revised in Generic Letter 82-12 and clarified in Generic Letter 83-14.
The Authority considers that, in this case, administrative control is more appropriate than technical specifications which would place an unnecessary and unreasonable burden on the plant staff and would divert resources that could be appropriated more usefully.
(3)
Dedicated Hydrogen Penetrations (II.E.4.1)
Since the James A.
FitzPatrick Nuclear Power Plant does not rely on external recombiners or purge /repressurization systems but on l
inerting as the primary means for post-accident combustible gas
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control of the containment atmosphere, this item is not applicable.
An inerted containment is maintained with a minimum amount of 02, as regulated by Technical Specifications.
The Authority is in the process or preparing a submittal which will address this question.
(4)
Containment Pressure Setpoint (II.E.4.2.5) 4 As stated in the Generic Letter, no further actions are required on this item.
(5)
Containment Purge Valves (II. E. 4. 2. 6 )
This item has been addressed and the proposed technical specifications submitted in Reference 2.
(6)
Radiation Signal on Purge Valves (II.E.4.2.7)
Technical Specifications for this item are not addressed at this time pending resolution by the NRC as stated in the Generic Letter.
(7)
Report SV and RV Failures and Challenges (II.K.3.3)
These technical specifications will be submitted under separate Cover.
(8)
RCIC Restart and RCIC Suction (II. K. 3.13, II.K.3.22)
These technical specifications will be transmitted under separate Cover.
r-(9)
Isolation of HPCI and RCIC Modification (II.K.3.15)
Since the James A.
FitzPatrick Nuclear Power plant does not use a time delay relay for this modification, this item is not applicable.
(10)
Interlock on Recirculation Pump Loops (II.K.3.19)
Since the James A.
FitzPatrick Nuclear Power plant has jet pumps, this item is not applicable.
(11)
Common Reference Level (II.K.3.27)
This technical specification was submitted in Reference 3 and approved in Amendment 67 to the FitzPatrick Operating License.
(12)
Manual Depressurization (II.K.3.45)
As stated in the Generic Letter, no technical specifications are required for this item.
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