ML20009A609
| ML20009A609 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/07/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.D.1, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.1, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.25, TASK-TM JPN-81-49, NUDOCS 8107130368 | |
| Download: ML20009A609 (10) | |
Text
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POWER AUTHORITY OF THE STATE OF NE'N YORK 10 CotuMaus CIRCLE NEW YORM, N. L 1o010 (212) 397 6200 GrenGar.stany TnUSTEES oramatino or, essa JO H N S.DYSCN JtiHN W. BOSTON seiosNT nocsounse
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Director of Nuclear Reactor Regulation TwouA. n. racy U. S. Nuclear Regulatory Commission
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washington, D. C.
20555 Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0737 Post-TMI Requirements I
I
Dear Sir:
)
I contains the Power Authority's response to the l
following NUREG-0737 items:
1 i
II.B.1 RCS Vents II.D.1 Safety Relief Valve Testing II.E.4.1 Dedicated Hydrogen Penetrations II.E.4.2.7 Closure of Containment Vent and Purge Valves on High Radiation II.F.1.3 Containment High Range Radiation Monitors II.K.3.13 Separation of HPCI and RCIC Initiation Levels II.K.3.15 HPCI and RCIC Isolation II.K.3.25 Effects of Loss of Power on Pump Seals III.A.2 Long-Term Emergency Preparedness (also identified as NUREG-0654 Rev. 1 Appendix 2 Meteorological Criteria for Emergency Preparedness)
If you have any further. questions please do not hesitate t
to contact us.
4 Very truly yours, if QSI' p
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J Bayne S7 d-' h U
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enior Vice resident I'*
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ITEM II.B.1 REACTOR COOLANT SYSTEM VENTS Since JAFNPP is a G.E.
BWR 4, the generic positions expressed by the GE/BWR Owner's Group, regarding BWR 4 RCS venting, are applicable to our facility.
This includes the recent response to NRC questions D.B Waters (GE/BWR Owner's) to D.
G. Eisenhut (NRC) dated April 24, 1981) regarding procedures and HPCI/RCIC operations.
The Authority provided a detailed description of the JAFNPP RCS venting capability in a previous letter from P.
Early (PASNY) to D.G. Eishenhut (NRC) dated December 22, 1979 (JPN-79-65).
Procedures for venting of the JAFNPP RCS are contained in F-OP-65 Start Up and Shutdown Procedure.
The Authority is also participating with the GE/BWR Owner's Group in the development of emergency procedure guidelines which will address the venting of the RCS through the operation of the HPCI, RCIC and ADS Systems.
j
ITEM II.D.'l SAFETY AN"D RELIEF VALVE TESTING The preliminary generic BWR safety and relief valve test results have been transmitted by the BWR Owner's Group in a letter from T.J.
Dente (BWR Owner's Group)to D.G. Eisenhut (NRC) dated July 1, 1981.
A preliminary review by the Authority of these results indicated that the type of valves used at JAFNPP (two-stage Target Rock) performed satisfactorily under the test conditions.
i 1
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II.E.4.1 DEDICATED HYDROGEN PENETRATIONS The Power Authority has responded to this item in a letter from J.
P.
Bayne (PASNY) to T.A.
Ippolito (NRC) dated April 28, 1981 (JPN-81-31).
This letter requested an extension of the implementation date from July 1, 1981 to June 1982 for material availability reasons.
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II.E.4.2.7 CLOSURE OF. CONTAINMENT VENT AND PURGE VALVES ON HIGH-RADIATION The Power. Authority is implementing the requirements of NUREG-0737 Item'II.F.1.3 for the installation of drywell highfradiation monitors.
At this time, engineering work is-
- also in progress for a. plant modification to. utilize a signal from these new monitors to close the vent and purge valves on high radiation drywell..The Authority intends to complete.this modification concurrently with the modification required by Item II.F.1.3..' Dependent upon material availability both will be completed by January 1, 1982.
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ITEM II.F.1.3 CONTAINMENT IIIGII RANGE RADIATION MONITORS The Power Authority is in the process of implementing the requirements of this item.
The following General Atomics equip-ment is being procured:
Gamma Dectector Model No. RD23 l
Readout Module Model No. RP2C
)
Power Supply Model No. RP23 i
Nimbin Model No. RP20-01 These components meet the specifications in NUREG-0737 Table II.F.1-3.
They will be installed at Elevations 282 and 291 in the drywell in physically separate locations. The attached sketch shows the detector locations.
The final design details are expected to be available by August 1, 1981.
The detectors will be installed during the
/
October refueling outage and operational, as required, by January 1, 1982.
)
-II.K. 3.13 SEPARATION OF hPCI AND RCIC INITIATION _ LE1'ELS The Power Authority has responded to this item in a letter from J.P. Bayne (PASNY) to T. A.
Ippolito (NRC) dated April 28, 1981 (JPN-81-31).
This letter requested an extension of the implementation date from July 1, 1901 to October 1982 for material availability reasons.
/
4 J
ITEM II.K.3.15 HPCI AND RCIC ISOLATION The Power Authority has responded to this item in a letter from J.
P.
Bayne (PASNY) to T.A.
Ippolito (NRC) dated Janaury 8, 1981 (JPN-81-5). This letter explained that a plant modification to address this item was completed at the JAFNPP in March 1975.
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ITEM II.K.3.25 EFFECT OF LOSS OF POWER ON PUMP SEALS The BWR Owner's Group has provided a generic analyis of this item in a letter from D.
B. Waters (BWR Owner's Group) to D.G.
Eisenhut.(NRC) dated January 23, 1981.
This analysis applies to the JAFNPP and is endorsed by the Authority.
ITEM III.A.2 LONG-TERM EMERGENCY PREPAREDNESS
( ALSO IDENTIFIED AS NUREG- 0654 Rev.1 APPENDIX 2 METEOROLOGICAL CRITERIA FOR EMERGENCY PREPAREDNESS)
The Power Authority and Niagara Mohawk are providing a common meterological tower for the James A. FitzPatrick and Nine Mile Point nuclear facilities.
The functional description of the tower and instrumentation has been submitted to the NRC in a letter from D.P.
Dise (i'tagara Mohawk) to D.G. Eisenhut (NRC) dated June 30, 1981.
As stated in that letter it is anticipated that the meteorological system will be installed and operational by July 1, 1982.
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