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Amend 123 to License DPR-16,revising Tech Specs to Allow Continued Power Operation for Cycle 11 If Both Primary & Backup Safety Valve Indicators Become Inoperable on No More than Two Safety Valves & Making Administrative Changes
	ML20196K311
Person / Time
Site:	Oyster Creek
Issue date:	06/28/1988
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; GPU Nuclear Corp, Jersey Central Power & Light Co
Shared Package
ML20196K315	List: ML20196K311; ML20196K327;
References
	DPR-16-A-123 NUDOCS 8807060572
	Download: ML20196K311 (5)
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UNITED STATES NUCLEAR REGULATORY COMMISSION t

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OPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDHENT TO PROVISIONAL OPERATING LICENSE Amendment No.123 License No. OPR-16 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by GPU Nuclear Corporation, et al.,

(the licensee), dated April 29, 1988, as supplemented May 11, 1988, 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 conformity 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 amendment can te 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 comon 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.

I 8807060572 880628 ADOCK0500g9 DR l

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- 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Provisional Operating License No. OPR-16 is her(ey

- amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Araendment No.123, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of issuance.

THE NUCLEA GUL ORY OMfISSION l

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v Jo n F. Stolz, D$ rector j P oject Directorate I-4 ivision of Reactor Projects I/II s Office of Nuclear Reactor Regul0 tion

Attachment:

Changes to the Technical Specifications Date of Issuance:

June 28,1988

t ATTACHMENT TO LICENSE AMEN 0HENT h0.123 PROVISIONAL OPERATING LICENSE NO. OPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remova Insert

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Page 3,13-1 3.13-1 Page 3.13-2 3.13-2 i

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'3.13 ACCIDENT MONITOR!NG INSTRUMENTATION i

Applicability:

Applies to the operating status of accident monitoring i nstrumenta tion.

Objective:

To assure operability of accident monitoring instrumentation.

Specification:

A.

Relief Valve Position Indicators, 1

The accident monitoring inst.rumentation channels shown in Table 3.13.1 shall be OPERABLE when the mode switch is in l

the Startup or Run positions.

2.

With the r. umber of OPERABLE accident monitoring l

instrumentation channels less than the Total Nuniber of Channels shown in Table 3.13.1, either restore the inoperable channels to OPERABLE status within 7 days, or place the reactor in the SHUT 00WN CONDITION within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

With the number of OPERABLE accident monitoring l

instrumentation channels less than the Minimum Channels Operable requirements of Table 3.13.1, either restore the inoperable channel (s) to the OPERABLE status witnin 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or place the reactor in the SHUTOOWN CON 5! TION withir. the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B.

Safety Valve Position Indicators 1

During POWER OPERATION, both primary

and backup ** safety valve monitoring instruments tre required to be OPERABLE except as provided in 3.13.B.;' and 3.13.B.3.

2.

If either the primary

or backup ** accident monitoring instruments on a valve become inoperable, the primary

accident mon'toring instrumeni. 9n an adjacent valve must be OPERABLE, and its set point appropriately reduced.

(see NOTE below) 3.

If both the primary

and backup ** accident monitoring instruments on a valve become inoperabic and the primary

accident monitoring instrument on an adjacent valve is ODERABLE, either restore the ir. operable e:hanr.el(s) to an OPEheLE status within 7 days, or place the reactor in tne SHUTOOWN CONDITION within the next '!4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

(see NOTE below)

Acoustic Monitor NOTE:

During Cycle 11 only, the provisions or

- Thermocouple Specification 3.13.B.2 do not apply to backup **

accident monitoring instruments.

In addition,

(

continued POWER OPERATION is permitted if both the l

primary

and backup ** accident monitoring instruments become inoperable on a maximee of two (2) safety valves.

The 7 day action statement in Specificatinn 3.13.B.3 will comence if both instruments on a third valve become inoperable.

OYSIER CREEK 3.13-1 Amendment No. : /,ff,3(,123 j

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If the rQquirements of Section 3.13.B.2 or 3.13.8.3 cannot be met within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , place the reactor in f

the SHUTDOWN CONDITION within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l C.

In the event that any of these monitoring channels become inoperable, they shall be made OPERABLE prior to startup following the next COLD SHUT 00WN.

D. Wide Range Torus Water Level Monitor 1.

Two wide range torus water level monitor channels shall be continuously indicated in the control room during Power Operation.

2.

With the number of operable accident monitoring cuannels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel (s) to Operable status within 7 days or. place the reactor in the shutdown condition within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

With the number of operable accident monitoring instrumentation channels less than the Minimum i

Channels operable requirements of Table 3.13.1, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or place the reactor in the shutdown condition within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

E.

Wide Range Drywell Pressure Monitor 1.

Two Wide Range Drywell Pressure monitor channels shall be continuously indicated in the control room during Power Operation.

2.

With the number of operable accident monitoring channels less than the total Number of Channels shown in Table 3.13.1, restore the inoperable channel (s) to Operable status within 7 days or place the reactor in the shutdown condition within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

With the number of operable accident monitoring instrumentation channels less than the Minimum Channels operable requirements of 3.13.1, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or place the reactor in the shutdown condition within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

F.

Drywell Hp Monitor 1.

Two drywell hydrogen monitor channels shall be capable of continuously indicating in the control room during power operation.

0YSTER CREEK 3.13-2 Amendment No.: p(, pf, f4, % 123 i

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ML20196K311

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