ML20214S951
| ML20214S951 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/04/1987 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | Corbin McNeil Public Service Enterprise Group |
| References | |
| NUDOCS 8706100065 | |
| Download: ML20214S951 (4) | |
Text
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June 4, 1987 Docket No.: 50-354 Mr. Corbin A. McNeill, Jr.
Senior Vice President - Nuclear l
Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038 f
Dear Mr. McNeill:
SUBJECT:
CONFIRMATION OF CHANGE TO TECHNICAL SPECIFICATIONS RE:
HOPE CREEK GENERATING STATION i
This confirms our telephone authorization given on Jure 4, 1987, for the change to the Technical Specifications for Hope Creek Generating Station, as i
requested on an emergency basis in your letter dated June 1, 1987 and supplemented with additional information by letter dated June 2 and 4, 1987.
Facility Operating License NPF-57 is amended on June 4,1987. The revised Technical Specification page 3/4 3-85, and the overleaf page, 3/4 3-86, are enclosed.
The formal license amendment, our completed safety evaluation, and the Federal Register Notice of this change to the Technical Specifications for Hope Creek Generating Station are being processed and copies of these documents will be j
sent to you in the near future.
Sincerely,
)
/s/
h[)NDO 5 003S4 Bruce A. Boger, Assistant Director P
PDR for Region I Reactors Division of Reactor Projects I/II i
Enclosures:
j Technical Specification Pages cc w/ enclosures:
See next page i
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June 4,1987 Docket No.: 50-354 Mr. Corbin A. McNeill, Jr.
Senior Vice President - Nuclear Public Service Electric and Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038
Dear Mr. McNeill:
SUBJECT:
CONFIRMATION OF CHANGE TO TECHNICAL SPECIFICATIONS RE:
HOPE CREEK GENERATING STATION This confirms our telephore authorization given on June 4, 1987, for the change to the Technical Specifications for Hope Creek Generating Station, as requested on an energency basis in your letter dated June 1,1987 and supplemented with additional infomation by letter dated June 2 and 4,1987.
Facility Operating License NPF-57 is amended on June 4,1987. The revised Technical Specification page 3/4 3-85, and the overleaf page, 3/4 3-86, are enclosed.
The fomal license anendment, our completed safety evaluation, and the Federal Register Notice of this change to the Technical Specifications for Hope Creek Generating Station are being processed and copies of these documents will be i
sent to you in the near future.
Sincerely.
Bruce A. Bo r, Assistant Director for Region I Reactors Division of Reactor Projects I/II
Enclosures:
Technical Specification Pages cc w/ enclosures:
See next page
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J
.i Mr. C. A. McNeill Public Service Electric & Gas Co.
Hope Creek Generating Station cc:
S. E. Miltenberger Mr. B. A. Preston, Manager Vice President - Nuclear Operations Licensing and Regulation Nuclear Department Nuclear Department P. O. Box 236 P. O. Box 236 Hancocks Bridge, NJ 08038 Hancocks Bridge, New Jersey 08038 Gregory Minor Susan C. Remis Richard Hubbard Division of Public Interest Advocacy Dale Bridenbaugh
.New Jersey State Department of MHR Technical Associates the Public Advocate 1723 Hamilton Avenue, Suite K Richard J. Hughes Justice Comples San Jose, California 95125 CN-850 Trenton, New Jersey 08625 M. J. Metterhahn, Esquire Conner & Wetterhshn Office of Legal Counsel Suite 1050 Department of Natural Resources 1747 Pennsylvania Avenue and Environmental Control Washington, D.C.
20006 89 Kings Highway P.O. Box 1401 R. Fryling, Jr., Esquire Dover, Delaware 19903 Law Department - Tower SE 80 Park Place Ms. Rebecca Green 2
Newark, New Jersey 07101 New Jersey Bureau of Radiation Protection l
380 Scotch Road Resident Inspector Trenton, New Jersey 08628 U.S. Nuclear Regulatory Conunission P.O. Box 241 Mr. Anthony J. Pietrofitta l
Hancocks Bridge, New Jersey 08038 General Manager Power Production Engineering Richard F. Engel Atlantic Electric Deputy Attorney General 1199 Black Horse Pike Division of Law Pleasantville, New Jersey 08232 Environmental Protection Section Richard J. Hughes Justice Complex Regional Administrator, Region I a
CN-112P U. S. Nuclear Regulatory Commission Trenton, New Jersey 08625 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. S. LaBruna l
General Manager-Hope Creek Operations Hope Creek Generating Station P.O. Box 118 Hancocks Pridge, New Jersey 08038 l
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x TABLE 3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION 9
m MINIMUM APPLICABLE REQUIRED NUMBER CHANNELS
'0PERATIONAL INSTRUMENT OF CHANNELS OPERABLE CONDITIONS ACTION t
1.
Reactor Vessel Pressure 2
1 1,2,3 80 i
2.
1 1,2,3 80 l
3.
Suppression Chamber Water Level 2
1 1,2,3 80 4.
Suppression Chamber Water Temperature
- 2 2
1,2,3 80(a) 5.
Suppression Chamber Pressure 2
1 1,2,3 80
)
6.
Drywell Pressure 2
1 1,2,3 80 1
7.
Drywell Air Temperature 2
1 1,2,3 80 w
h 8.
Primary Containment Hydrogen /0xygen Concentration Analyzer and Monitor 2
1 1,2,3 80 w
h 9.
Safety / Relief Valve Position Indicators (c) 2/ valve **
1/ valve **
1,2,3 80 10.
Drywell Atmosphere Post-Accident Radiation Monitor 2
1 1,2,3 81 11.
North Plant Vent Radiation Monitor #
1 1
1,2,3 81 12.
South Plant Vent Radiation Monitor #
1 1
1,2,3 81 k
13.
FRVS Vent Radiation Monitor #
1 1
1,2,3 81 14.
PrimaryCoginmentIsolationValvePosition n.,
Indication 2/ valve 1/ valve 1,2,3 82 7*&
g' g
- High range noble gas monitors.
gg
- Average bulk pool temperature.
4 g (a**) Acoustic monitoring and tail pipe temperature.
E*
Suppression chamber water temperature instrumentation must satisfy the availability requirements specified
- g (b)0ne channel consists of the open limit switch, and the other channel consists of the closed limit switch.
in Specification 3.6.2.1.
(c)The acoustic monitor for F013H SRV may be inoperable until September 21, 1987 or until the first forced outage of sufficient duration to effect repair prior to that date without applying the shutdown requirement of ACTION 80(a).
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I Table 3.3.7.5-1 (Continued)
ACCIDENT MONITORING INSTRUMENTATION ACTION STATEMENTS ACTION 80 -
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
With the number of OPERA 8LE accident monitoring instrumentation channels less than the Minimum Chrnnels OPERABLE requirements of Table 3.3.7.5-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 81 -
With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
a.
Initiate the preplanned alternate method of monitoring the appropriate parameter (s), and b.
Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
The provisions of Specification 3.0.4 are not applicable.
ACTION 82 -
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3.7.5-1, verify the valve (s) position by use of alternate indica-tion methods; restore the inoperable channel (s) to OPERABLE status kithin 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of
. Table 3.3.7.5-1, verify the valve (s) position by use of alternate
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indication methods; restore the inoper.tble channel (s) to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a a
HOPE CREEK 3/4 3-86
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