ML20072R325
| ML20072R325 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/13/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072R327 | List: |
| References | |
| NUDOCS 9103250094 | |
| Download: ML20072R325 (4) | |
Text
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UNITED STATES
!N NUCLE AR HEGULATDRY COMMISSION n
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PUBLICSERVICEELECTRit1GASC@PANY ATLtHTIC CITY ILECTRIC COMPANY D0CKET No. 50-304 HOPE CREEK GENERATING STATION i
AMENDHENT TO FACILITY OPERATING LICENSE Amendment No. 40 License No. NPF-57 1.
The Nuclear Regulatory Comission (the Comission 01 theNRC)hasfound that:
A.
The application for amendment filed by the Public Service Electric &'
Gas Company (PSE&G) dated December 28, 1990 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 it B.
The facility will operate in conformity with the applicatlon, the provisions of the Act, and the rules and regulations of the Comission; f
C.
There is ressonable asura,ce: (i) that the activities authorized by i
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 I; D.
The issuance of this amendment will nul be inimical t.o the comon defense and security or to the health ano safety of the public; and E.
The issuane.e of this amendment is in accordance with 10 CFR Part 51 of the Comission's regul tions ed all applicable requirements have been satisfied.
9103250094 910313 PDR ADOCK 05000354 P
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2.
Accordingly, facility Operating' License No. NPF.57 is hereby amended by changingLicenseCondition?.C.s5)toreadasfollows*:
2.C.(5)
Solid State Logic Modules i
PSE8G shall continue, for the life of the >1ont, a reliability program to monitor the performance of the 3ailey 862 SSLMs installed at Hope Creek Generating Station. This program should obtain relitbility data, failure characteristics, and root cause of failure of both safety.related and non. safety.related Bailey 862 SSLMs. The results of the i
reliability program shall be maintained on. site a*d made available to the-NRC upon request.
3.
This license amendment is effective as of its d5te of issuance and shall 1
be-implemented within sixty days of its date of iv.uance.
FOR THE Nt1 CLEAR REGULATORY COMMISSION j
/S/
Walter R. Butler, Directoc Project Directorate 1 '
Division of Reactor Projects. 1/11 Office of Huclear Reactor Regulation
Attachment:
o Page 4 of License
'Date of Isstance:
March 13. 1991
- Page 4 of the. License is attached, for convenience for the competite License to. reflect this change, o
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Accot dingly, Facility Operating (License No. NPF-57 is hereby amended by changing License condition 2.C. 5) to reed as follows*:
2.C.(5)
Solid State Logie Modules PSE8G shall continue, for the life of the slant, a reliability program to monitor the performance of the 3ailey 062 SSLMs installed at Hope Creek Generating Station. This program should obtain reliability data, failure characteristics, and root cause of failure of both safety related and non safety-related Bailey 862 S$ lits. The results of the reliability program chall be maintained on-site end made
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available to the NRC upon request.-
3.
This license amendment is effu tive as of its date of issuance and shall be implamented within sixty days of its date of issuance.
j FOR THE NUCLEAR REGULATORY COMMISSION
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t Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation 1sttachment:
Page 4 of License Date of Issuance:
March 13. 1991 Page 4 of the License is attached, for convenience for the composite License
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- to reflect this change.
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Intervi <
espection (Section 6.6, SER: Sections 5.2.4.'a and 6.6.3 [ lNo. 5)
PSE&G shall submit an inservice inspection pr39 ram in accordance a.
with 10 CFR 50.55a(g)(4) for staff review by October 11, 1986.-
b.
Pursuant to 10 CFR 50.55a(a)(3) and for the reasons sec forth in Sections 5.2.4.3 and 6.6.3 of SSER No. 5. the relief identified in the PSE&G submittal dated November 18, 1985, as revised by the submittal dated January 20, 1986, requesting relief from certain requ;rements of 10 CFR 50.55a(g) for the preservice inspection program, is granted.
(5) Solid State Logic Modules PSE&G shall continue, for the life of the plant, a reliability program to monitor the performance of the Bailey 86? SSLMs installed at Hope Creek Generating Station. This program should obtain reliability data, failure characteristics, and root cause of failure of both safety-related and non-safety-related Belier 952 SSLMs.
The results of tha "t 11 ability program shall be mbintained on-si'.. and made available to the NRC upon request.
(6) Fuel Storace and Handlino (Section 9.1, SSER No. 6) a.
No more than a total of three (3) fuel assemblies shall be out of approved shipoing containers or fuel assembly stcrage racks or the reactor at any one +ime, b.
The above three (3)-fuel assemblies as a group shall maintain a minimum edge-to-edge spacing of twelve (IE, inches from the shipping' container array and the storage rack array.
Fresh Fuel assemblies, when stored in their shipping con-c.
tainers, shall be stacked no more than three (3) containers high.
-(7) Fire Protection (Section 9.5.1.8. SSER No. 5: Section 9.5.1, 55ER No. 6)
-PSE&G shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety.
Analysis Raport for the facility through Amendment Po. 15 and as describeo in i+c submittal dated May 13, 1986, and as approved in ine SER cated Octoos.- 1984 (and Supplements 1 through 6) subject to the following provision:
PSE&G may make changes to the approved fire protection program wi+50ut prior approval of the Commission only if those changes wo.ed not adverscly affect the abi ity so achieve and maintain safe sh:tdown in the event of a fire.
Amendment NO-40 g
.