ML20055D589

From kanterella
Jump to navigation Jump to search
Amend 38 to License NPF-57,revising Tech Spec 5.6.3 Re Spent Fuel Storage Capacity
ML20055D589
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/21/1990
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20055D590 List:
References
NUDOCS 9007090147
Download: ML20055D589 (5)


Text

.

.s..,

,1

/,; m % q'o,,.

UNITED $TATES

+.

NUCLEAR REGULATORY COMMISSION l

e o

5 W ASHINGTON, D. C. 20$b6

  • ...+)

PUBt1C SERVICE ELECTRIC & GAS COMPANY ATLANTIC CITY ELECTRIC COMPANY.

DOCKET N0. 50-354 POPECREEKGENERAT1HGSTATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 38 License No. NPF-57 L

1.

.The Nuclear Regulatory Comission (the Comission or the NRC) has found l

that:

c n

A.

The application for amendment filed by the Public Service Electric &

Gas Company (PSE8G) dated October.11, 1989 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 i

t Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i

Comission, C.

There is reasonable assurance: (1) that the activities authorized by this amendment 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 set forth in 10 CFR Chapter 1; 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.

2.

Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-57 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan t'

The Technical Specifications contained in Appendix A, as revised through Amendment No. 38, and the Environmental Protection Plan contained in A>pendix B, are hereby incorporated in the license. PSE&G shall operate tie facility in accordance with the Technical Specifications and the Environmental Protection Pian.

9007090147 900621

{DR ADOCK 05000354 PDC

~

l l

.. 3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of its date of issuance.

FOR THE N0 CLEAR REGULATORY COMMISSION lh c

Walter R. Butler Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 21, 1990

ATTACHPENT TO LICENSE AMENDMENT NO. 38 FACILITY OPERATING LICENSE NO. NPF-57 OOCKET N0. 50-354 Replace the following pages of the Appendix 'A" Technical Specifications with the attached pages. The revised page is identified by Amendment number and contains vertical lines irdicating the area of change. Overleaf page provided to maintain document completeness.*

Remove Insert 5-5 5-5 56 5 6*

l

'ji t

DESIGN FEATURES i

56 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

A k,ff equivalent to less than or equal to 0.95 when flooded with a.

i unborated water, including all calculational uncertainties and biases -

as described in Section 9.1.2 of the FSAR.

i b.

A nominal 6.308 inch center-to-center distance between fuel assemblies i

placed in the storage racks.

5.6.1.2 The k,ff for new fuel for the first core loading stored dry in the

[

spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.

ORAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent

' inadvertent draining of the pool below elevation 199' 4".

CAPACITY 5.6.3 The spent fuel storage pool shall be limited to a storage capacity of no more than 4006 fuel assemblies.

l 5.7 COMPONENT CYCLIC On TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1-1.

t 9

HOPE CREEK 5-5 Amendment No. 38

I r

5 3

in8tE 5.1.1-1 aE

.. Q CONSEE CELIC OR TRA8ISIEN ListITS-CVCLIC OR SESIGII CELE l

C0fr0KM TRAIISIEN LIIIIT st TaAff5IEM I

4

)

Reacter 129 Iwatap and cooldsun cycles 78T to 546T to IST j

Less of feedseter hosters

-SS step change cycles 300 reacter trip cycles 10E to E of ARTED TEWIRL PEMER

.138 hydrostatic pressure and Pressurized to > 930 and leak tests

<1250 psig I

i Y

f i

i j

t i

t I

i

[

[

i i

i k

t h

I

,e

. *~

t i

_