ML20035A249
| ML20035A249 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/18/1993 |
| From: | Mccabe B Office of Nuclear Reactor Regulation |
| To: | Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| TAC-M85879, NUDOCS 9303250051 | |
| Download: ML20035A249 (4) | |
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- ,4 It UNITED STATES y
E.j NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555-0001
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March 18,1993 Docket No. 50-333 Mr. Ralph E. Beedle Executive Vice President, Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Beedle:
SUBJECT:
CHANGE TO THE BASES OF THE TECHNICAL SPECIFICATIONS - JAMES A.
FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M85879)
By letter dated February 22, 1993, the Power Authority of the State of New York (PASNY) proposed revising James A. FitzPatrick Technical Specification (TS) Bases Section 3.1.B and adding Bases Section 3.1.C.
The proposed revision to TS Bases Section 3.1.8 deletes the specific initial Loss-of-Coolant Accident (LOCA) Minimum Critical Power Ratio (MCPR) parameter used as an assumption for LOCA analyses and replaces it with a reference to the applicable LOCA analyses. The new TS Bases Section 3.1.C provides applicable references. The NRC staff has reviewed the proposed changes to the TS Bases and offers no objection.
Enclosed is a copy of the revised Bases page 35. All staff activities related to TAC No. M85879 cre considered complete.
Sincerely,
$(
/A M Brian C. McCabe, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Bases 35 cc w/ enclosure:
See next page
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9303250051 930318 PDR ADOCK 05000333 60 p
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Mr. Ralph E. Beedle James A. FitzPatrick Nuclear Power Authority of the State of New York Power Plant cc:
j Mr. Gerald C. Goldstein Ms. Donna Ross Assistant General Counsel New York State Energy Office Power Authority of the State 2 Empire State Plaza of New York 16th Floor 1633 Broadway Albany, New York 12223 New York, New York 10019 Resident Inspector's Office U. S. Nuclear Regulatory Commission Post Office Box 136 Lycoming, New York 13093 Mr. Harry P. Salmon, Jr.
Resident Manager James A. FitzPatrick Nuclear Power Plant Post Office Box 41 Lycoming, New York 13093 i
Mr. J. A. Gray, Jr.
Director Nuclear Licensing - BWR Power Authority of the State of New York 123 Main Street White Plains, New York 10601 Supervisor Town of Scriba Route 8, Box 382 Oswego, New York 13126 Mr. John C. Brons, President Power Authority of the State of New York 123 Main Street White Plains, New York 10601 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Regicnal Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406
JAFNPP 3.1 BASES (cont'd)
Turbino control valves fast closure initiates a scram based on C.
References pressure switches sensing electro-hydraulic control (EHC) system oil pressure. The switches are located between fast 1.
General Electric Topical Report NEDO-21662, closure solenoids and the disc dump valves, and are set Revision 2. " Loss-of-Coolant Accident Analysis relative (500< P< 850 psig) to the normal (EHC) oil pressure of Report for James A. FitzPatrick Nuclear Power Plant 1,600 psig so that based on the small system volume, they (Lead Plant)," July 1977 with errata and addenda.
can rapidly detect valve closure or loss of hydraulic pressure.
2.
General Electric Topical Report NEDC-31317P, The requirement that the IRM's be inserted in the core when
" James A. FitzPatrick Nuclear Power Plant the APRM's read 2.5 indicated on the scale in the start-up and SAFER /GESTR-LOCA Loss-of-Coolant Accident refuel modes assures that there is proper overlap in the Analysis," October 1986 with revisions, errata and neutron monitoring system functions and thus, that adequate addenda.
coverage is provided for all ranges of reactor operation.
B.
The limiting transient which determines the required steady state MCPR limit depends on cycle exposure. The operating limit MCPR values as determined from the transient analysis in the current reload submittal for various coro exposures are specified in the Core Operating Limits Report (COLR).
The ECCS performance analyses assumed reactor operation will be limited to the MCPR value for each fuel type as described in NEDO-21662 (Referencol) and NEDC-31317P (Reference 2) including the latest revision, crrata and addenda.
The Technical Specifications limit operation of the reactor to the more conservative MCPR based on consideration of the limiting transient as specified in the COLR.
Amendment No. f, %,1/9,1[2, Revised by NRC letter dated 3/18/93 35
-l March 18,;1993
. Docket No. 50-333 Mr. Ralph E. Beedle l
Executive Vice President, Nuclear Generation Power Authority of the State of i
New York 123 Main Street J
i White Plains, New York 10601
Dear Mr. Beedle:
l
SUBJECT:
CHANGE TO THE BASES OF THE TECHNICAL SPECIFICATIONS - JAMES A.
FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M85879) j By letter dated February 22, 1993, the Power Authority of the State of New York (PASNY) proposed revising James A. FitzPatrick Technical Specification'
)
(TS) Bases Section 3.1.B and adding Bases Section 3.1.C.
The proposed revision to TS Bases Section 3.1.B deletes the specific initial Loss-of-i Coolant Accident (LOCA) Minimum Critical Power Ratio (MCPR) parameter used as
]
an assumption for LOCA analyses and replaces it with a reference to the j
applicable LOCA analyses. The new TS Bases Section 3.1.C provides applicable references. The NRC staff has reviewed the proposed changes to the TS Bases-and offers no objection.
I Enclosed is a copy of the revised Bases page 35. All staff activities 'related to TAC No. M85879 are considered complete.
Sincerely, Original signed by:
l Brian C. McCabe, Senior Project Manager Project _ Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
Bases 35 l
cc w/ enclosure:
See next page l
Distribution.
See next page l
OUICE PDI-1:LA PDI-1:Pih,s PDI-1:D BMcCab b RACapra l
KAME CVogan tN DATE 3/13/93 3//7/93 9 //7/93
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/ /
l OFFICIAL RECORD COPY FILENAME: G:\\FITZ\\ FIT 85879.LTR i
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i Docket; File NRC & Local PDRs PDI-I Reading S. Varga, 14/E/4 J. Calvo,14/A/4 R. Capra l
C. Vogan B. McCabe e
OGC-WF D. Hagan, 3302 MNBB G. Hill (2), PI-22 Wanda Jones, P-370 C. Grimes, ll/F/23 P. Eselgroth, Region I ACRS (10) 3 OPA OC/LFDCB PD plant-specific file i
C. Cowgill, Region I cc: Plant Service list h
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