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Amend 74 to License DPR-16,changing Tech Specs to Include Action Statements Applicable to Loss of Secondary Containment Integrity
	ML20092N380
Person / Time
Site:	Oyster Creek
Issue date:	06/19/1984
From:	Crutchfield D; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20092N382	List: ML20092N380; ML20092N391;
References
	NUDOCS 8407030079
	Download: ML20092N380 (7)
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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f GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO THE PROVISIONAL OPERATING LICENSE Amendment No. 74 License No. DPR-16 1.- The Nuclear Regulatory Commission (the Commissior,) has found that:

A.

The application Tor amendment by GPU Nuclear Corporation and Jersey Central Power _ad Light. Company (the 14cer.see'.) Jated July 18, 1983 as supplemented Februery 1

...e na* % IP, 1984,

-compiles with the standards and < quirements of the Atomic Energy Act.of 1954, as amended (the Act), and the Commission's rules and regulations set forth in )0 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 I

Commission; C. ' There is reasonable assurance (i) that t!

octivities aethorized by this amendment can be conducted withNC enaangering the health and safety of the public; and (ii) that such activities will be conducted in~ compliance with the Commission'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 Commission's regulations and all applicable requirements have been satisfied.

8407030079 840619 PDR ADOCK 05000219 P

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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.

1 DPR-16 is hereby amended to read as follows:

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Technical Specifications l

1 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 74, 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 its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION V

Dennis M. Crutchfield, Chief Operating Reactors Branch #5 l

Division of Licensing l

Attachment:

Changes to the Technical Specifications Date of Issuance: June 19, 1984 l

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.u e ATTACHMENT TO LICENSE AMENDMENT NO. 74

'PROVISIONALOPERATINGLIbENSENO.'OPR-16 a

' b DOCKET NO. 50-219 g

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.- c Replace the following pages of Appendix A Technical Specifications with

-the enclosed pages.

The revised pages are/fdentified by the captioned

amendment number and contain vertical lines indicating the area of change.

PAGES 3.5-3a 3.5-3b 3.5-4 3.5-7 O

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3.5-3a If the diffdrential pressure of Spetification 3.5.A.9a cann t be maintained, and the differential pressure cannot be restored within the's.ubsequent 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period, an orderly shutdown shall be initiated and the reactor shall be in the shutdcwn condition within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and the cold shutdown condition within the following 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

Instrumentation to measure the drywell to suppression chamber differential pressure and the torus water level shall be operable at any time the differential pressure is required to be maintained by Specification 3.5.A.9.a.

Operation may continue for up to thirty days wlth one instrument cut of service.

If both differential pressure or both water level instruments are not operable, or if one instrument is out of service for more than thirty days, and such indication cannot be restored in the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the reactor shall be in the shutdown condition within the following 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months .

B.

Secondarv Containment

1. Secondary ' containment integrity shall be maintained at all times unless all of the following conditions are met:-

a)

The reactor is subcritical and Specification 3.2.A is met.

b)

The reactor is in the cold s'hutdown condition, c)

The reactor vessel head or the drywell head are t'n ' place.

d)

Ito work is being performed on the reactor or its connected systems in the reactor building which could result in inadvertent releases of radioactive material.

e)

No operations are being performed in, above, or around the spent fuel storage pool that could cause release of radioactive materials.

1.1 Upon the accidental loss of secondary containment integrity, restore seco,nd,ary containment integrity within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or:

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a)

During Power Operation:

1) Have the reactor mode switch in the shutdown mode position within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2) Cease all work on the reactor or its connected systems in the reactor building which could result in inadvertent releases of radioactive materials.

3) Cease all cperations in, above or around the Spent Fuel Storage Pool that cculd cause release of radioactive materials, b)

During refueling:

1) Cease fuel handling operations or act'vities which could M e rc e r,t 't o.

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a+ reduce the-shutdown margin (excluding reactor coolant i temperatuie changes).

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2) Ceas'e all work on the reactor or its connected systems in

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-the. reactor. building which could result.in inadvertant i

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releases of radioactive materials.

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3)' Cease all operations in, above or around the Spent Fuel

' Storage., Pool-that could cause release-of radioactive l materials.

2.

Two separate. and independent standby gas treatment system circuits shall

-be; operable _ when secondary containment is required except as specified by

' Specification 3.5.B.3.

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3.5-4 3.

With one-sta'ndby gas treatment system circuit inoperable:

a.

During Power Operation:

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1. Demonstrate the operability of the other standby gas treatment system circuit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and

-2.

Continue to demonstrate the operability of the standby gas treatment system circuit once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months until the inoperable standby gas treatment circuit *is returned to operable status.

,3.

Restore the inoperable standby gas treatment circuit to operable status within 7 days or be suberitical with reactor coolant temperature less than 212'F within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

l b.

During Refueling:

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Demonstrate the operability of the redundant standby gas treatment system within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and 2.

Continue to demonstrate the operability of the redundant standby gas _ treatment system once per 7 days until the inoperable system is returned to operable status.

3.

Restore the inoperable standby gas treatment system to operable. status within 30 days or cease all spent fuel handling, core alterations or operation that could reduce the shutdown margin (excluding reactor coolant temperature changes).

4.

If Specifications 3.5.B.2 and 3.5.B.3 are not met, reactor shutdown shall be initiated and the reactor shall be in the cold shutdown condition.within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the condition of-Specification 3.5.B..l.

l shall be met.

Bases:

- S pecific a t ions are placed on the operating status of the containment systems to assure their availability to control the release of any radioactive materials from irradiated fuel in the event of an accident condition.

The primary containment system (1) provides a barrier against uncontrolled release of fission products to the environs in the event of a

- break in the reactor coolant systems.

Whenever the reactor coolant water temperature is above 212*F, failure o'f the reactor coolant. system would cause rapid expulsion of the coolant from the reactor with an associated pressure rise in the primary containment.

~ Primary containment is required, therefore, to contain the thermal energy of the expelled coolant t

1 Amendnent No. lA 74 s

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containment ~ is : required during fuel handling operations and whenever work is being. performed. on.the reactor or its connected systems in the reactor

. building sin ~ce' their operation could result in inadvertent release of radioactive material.

When secondary containment is not maintained, the additional restrictions onJoperation and maintenance give assurance that the probability:of inadvertent releases of radioactive. material will be minimized.

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Maintenanc'e' will not, be performed on systems which connect to the reactor 3

, vessel lower than the - top of the active fuel unless the system is isolated by at -least one locked closed isolationsvelve.

The standby gas treatment system (6) filters and exhausts the reactor build'ing _ atmosphere to the~ s tack during secondary containment isolation conditions, with a minimum release of radioactive materials from the reactor building to-the environs.

Two separate filter; trains are provided each having.100% capacity. (6)

If one~ filter train becomes inoperable, there is no immediate threat to secondary containment and. reactor operation may continue while repairs are (being made._

Since the test interval for this system is one month

.(Specification 4.5), the time out-of-service allowance of 7 days is based fon-c on s id e ra tions presented in the Bases.in Specification 3.2 for a lone-out-of-two system.-

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References:

L(1) ' ' FDSAR, Volume I, Section V-1 (2) FDSAR, Volume I, Seetion V-1.4.1 (3) FDSAR, Volume I, Section V-1.7

!(4) Licensing Application, Amendment 11, Question III-25 (5) FDSAR,-Volume I,.Section V-2

-(6)

FDSAR,' Volume.I,: Section V-2.4 (7) Licensing Application, Amendment 42

(8) LicensingApplciation, Amendment 32, Question 3 (9) Robbins, C.

H., " Tests on a Full Scale 1/48 Segment 3

of the Humboldt Bay Pressure Suppression Containment,"

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.GEAP-3596, November 17, 1960..

h, (10) Bodega Bay Preliminary Hazards Summary Report, Appendix I, Docket 50-205, December 28, 1962.

(11) Report H. R. : Erickson, Bergen-Paterson to K. R. Goller, NRC, October 7, 1974.

Subject:

Hydraulic Shock Sway Arrestors.

In'. conjunction with the Mark I Containment Short Term Program, a plant

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unique analysis :vas ' performed on August 2, 1976, which demonstrated a L

factorL'of safety of at least two for the weakest element in the supprassion F

chamber support system.

The maintenance of a drywell-suppression chamber U

dif f e rential pressure.within the range shown on Figure 3.5-1 with a

suppression' chamber water level corresponding to a downcomer submergence L

range,of 3.02 to 5.3~ feet will assure the integrity of the suppression

. chamber when = subjected to post-LOCA suppression pool hydrodynamic forces.

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. Amendment No.. 14,-18, 52, 46 74

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ML20092N380

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