ML20004F978
| ML20004F978 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 06/18/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004F979 | List: |
| References | |
| NUDOCS 8106260389 | |
| Download: ML20004F978 (6) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION g
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WASHING TON. D. C. 20066
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POWER AUTHORITY OF THE STATE OF NEW YORK DOCKET NO. 50-333 JAMES A. FITZPATRICK NUCLEAR GENERATING PLANT AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-59 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The appitcation for amendment by Power Authority of the State of New York (the licenseel dated July 26,1970, as supplemented by filings dated May 15, June 22, September 25. -October 10, and November 29,1979, April 1. April 31 and October 31,1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in qonfonnity with the application, the. provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendnent can be conducted without endangering the health and safety of the public, and (ii) that such' activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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, 2.
Accordingly, Facility Operating License No. DPR-59 is amended by changes to the Technical Specifications as indicated in the attachment, and. Paragraph 2.C(2) of Facility Operating License No. DPR-59 is hereby r. mended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license.. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMISSION s
sistant Director for Operating Reactors Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: June 18, 1991 l
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ATTACHMENT 70 LTCENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. DPR-59 DOCKET NO. 50-333 Revise Appendix A Technical Specifications as follows:
Delete Replace 115' 115 245 245 246 246 9
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4 3.5 (cont'd)
JAFNPP 4.5 (cont'd) b.
From the time that the b.
When it is determined that LPCI mode is made or found the LPCI mode is inoper-to be inoperable for any able, both Core Spray repson, continued reactor Systems, the containment
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operation is permissible spray subsystem,-and the during the succeeding 7 emergency diesel gene-days unless the LPCI mode rators shall be is made operable earlier demonstrated to be provided that during these operable immediately and 7 days all active daily thereafter.
components of both Core Spray Systems, the containment spray sub-c.
The power source disconnect system (including two RHR and chain lock to motor-3 pumps).and the emergency operated RHR cross-tie valve, diesel generators shall be and lock on manually operated
- operable, gate valve shall be inspected once each operating cycle to i
c.
When the reactor water verify that both valves are t
3' teyratureisgreaterthan closed and locked.
212 F the motor operator for the RHR cross-tie valve (MOV20) shall be maintained disconnected from its electric power source. It shall be main-4 l
tained chain-locked in the closed position. The manually operated gate valve (lO-RHR-09) in the cross-tie line, in series with the motor operated valve, shall be maintained locked in the closed position.
- 4. a.
The reactor shall not be started up with the RHR System supplying cooling to the fuel pool.
J b.
The RHR System shall not supply cooling to the spent fuel pool when the reactor 0
coolant temperature is above 212.
i Amendment No. 55 115
1 JAPHPP i
- t-D.
The. reactor core contains 137
.5. 0 pESIGN FEATUNES cruciform-shaped control rods au described in Section 3.4 of 5.1 SITE the PSAR.
f A.
The James A. FitzPatrick Huclear Power Plant is located on the PASHY 5.3 REACTOR PRESSURE VESSEL portion of the Nine Mile Point site, The reactor pressure vessel is as approximately 3,000 f t. east of the described in Table 4.2-1 and 4.2-2 Hine Milu Point Nuclear Station..
of the FSAR.
The applicable design The NHP-JAP nite is on Lake Ontarlp coiles are described in Section 4.2 i
in Ouwego County, New York, approxi-l of the PSAR.
mately 7 miles northeast of Oswego.,
f The plant is located at coordinates parth 4,819, 545.012 m, east 386,968 945 m, 5.4 CONTAINMENT l
on the Universal Transverse Murcatdr The principal' design parameters A.
System.
and characteristics for tha primary containment are given in u.
The nearest point on the property Table 5.2-1 of the FSAR.
i line from the reactor building and j
any points of potential gescous The secondary contiainment is as D.
effluents, with the exception of the described in Section 5.3 and the lake shoreline, is located at the applicable codes are as, described
- i northeaut corner of the property.
in Section 12.4 of ths FSAR.
Thia distance is approximately 3,200 ft. and is the radius of the
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excluulon areas as defined in 10 CFH C.
Penetrations of the primary con-tainment and piping passing. t.hrough 100.3.
such penetrations are designed in.
accordance with standards met forth 5.2 HEACTOR in Section 5.2 of the FSAR.
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A.
The reactor core consists of not more than 560 fuel assemblies. For 5.5 FUEL STORAGE '
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the current cycle four funi typen i
are present in the core:
- 7x7, A.
The new fuel storage facility design i
dry 8 x 0, 8 x,SR and PS x 8R.
These fuel criteria are to maintain a Keff
<0.90 and flooded <0.95.
j typeu nro doncribed in fioction 3.2 of the Compliance shall be ve'rified prior to i
FSAH and HEpo-24011.
The 7 x 7 fuel han 49 introduction of any new fuel design ruel roda, the 8x a fuel has 63 fu9l to this facility.
roda and I water rod, and the o x ou asul-l Pil x 8R fuel have 62 fuel rods and 2 water 1
roilu.
f 245 3fi, f (d 55 Amenilment No.
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,g V 5.5.(cont'd)
JAFNPP B.
The spent fuel storaqo pool is designed to maintain K gg e
<0.95 under all conditions as described,in t! e Authority's application for rsent fuel i
storage modification transmitted i
to NRC July 26, 1978.
In order to assure that the criteria is met, new fuel average enrichment will be limited to < 3.3 w/o U-235. The number of fuel asse'iiiblies stored in the spent fuel pool shall not exceed 2244.
Y 5.6 SEISMIC DESIGN The reactor building and all. engineered s:feguards are designed on basis of dy-namic analysis using acceleration re-
- rponse spectrum curves which are nor-malized to a ground motion of 0.08 g.
for the Operatlng Basis Earquake, and O.15 g, for the Design Basis Earthquake.
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