ML20066D379

Application for Amend to License DPR-16,consisting of Tech Spec Change Request 194,changing Pages 3.3-1,3.3-5,3.3-6, 3.3-7,3.3-8,3.3-8a,3.3-9,3.3-9a,3.3-9b,3.3-9c,4.3-1 & 4.3-2 to Incorporate New pressure-temp Limits Up to 17 EFPY

ML20066D379
Person / Time
Site:	Oyster Creek
Issue date:	01/11/1991
From:	J. J. Barton GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20066D374	List: ML20066D373 ML20066D379 ML20066D387 ML20066D398
References
NUDOCS 9101150019
Download: ML20066D379 (5)

Text

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OPU NUCLEAR CORPORATION I

OYSTER CREEK NUCLEAR GENERATINO STATION Provielonal Operating )

License No. DPR.16

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Technical Specification Change Request No. 194 Docket No. 50-219

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Applicant.submite, by this. Technical Specification Change Request No. 194 to  !

the Oyster Creek Nuclear Generating Station Technteal Specificatione, a l chango to pages 3.3-1, 3.3-9, 3.3-6, 3.3-7, 3.3-0, 3.3-Ba, 3.3-9, 3.3-9a, 3.3-9b, 3.3-9c, 4.3-1 and 4.3-2.

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By /

d. J .,.kirton I Dbydetor, Oyster Cerek l l

Sworn and Subscribe to before me thie // b dayof(  ; 1991.

1 J Notary Public of NJ W '

JUDfTH M. CROWE Notory PuWic of New My Commission W /

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9101150019 910111 1 PDR ADOCK 05000219 l P PDR I 1

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' UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In'the Mattergof':

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}- Docket No. 50-219 GPU. Nuclear Corporation .)

~ CERTIFICATE OF SERVICE

=- This . is to certify that = a copy of Technical Specification -Change Request iha. l' 1944 for Oyster Creek Nuclear Generating. Station Technical Specifications, filed'with'the U.S. Nuclea'r Regulatory Commission on January 11, 1991

-has this day of; -January 11, 1991 , been served on the Mayor of  ;

Lacey. Township, Ocean County,-New Jersey by deposit in the United States

-. mail, addressed as'follows:

The Honorable Debra Madensky

' Mayor of Lacey Township 818 West Lacey Road q Forked' River, NJ 08731 By _

J. .

.Bal ton Dir ' tor, Oyster Creek i

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- OYSTER CREEK WUCLEAR GENERATING STAT 80N PROVISIONAL OPERATING LICENSE No. DPR-16 DOCKET NO. 50-219 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 194 Applicant hereby requests the Commission to change Appendix A to the above captioned license as below, and pursuant to 10 CFR 50.91, an analysis concerning the determination of no significant hazards consideration is presented below:

1.0 SECTIONS TO BE CHANGED Section 3.3.A(iv) and Bases section 3.3.B and Bases References curves (a),(b) and (c) in Figure 3.3.1 Section 4.3.A and Bases 2.0 EXTENT OF CHANGE

1) Section 3.3. A(iv) and curves (a),(b) and (c) in Figure 3.3.1 are revised to provide new pressure-temperature (P-T) operating curves for operation up to 17 effective full power years (EFPY) and,

11) Section 3.3.B is revised to provide a new reactor vessel temperature limit for full tensioning of the reactor vessel closure head studo, 111) Current Oyster Creek Technical Specifications show P-T operating curves in three (3) different figures. Technical Specification Change Request No. 194 provides all three (3) P-T curves in one figure (Figure 3.3.1). To reflect this arrangement, editorial changes are made in Section 3.3.A and its Bases, and Section 4.3.A and its Bases.

3.0 CHANGES REOUESTED The changes are shown on the attached Technical Specification pages 3.3-1, 3.3-5, 3.3-6, 3.3-7, 3.3-8, 3.3-8a, 3.3-9, 4.3-1 and 4.3-2.

4.0 DISCUSSION The purpose of this Technical Specification Change Request is to revise the Technical Specifications to incorporate new pressure-temperature (P-T) limits and a new reactor vessel temperature limit for full tensioning of the reactor vessel closure head stude (boltup 1 temperature). Followlag discussion supports these proposed Technical Specification changes:

Chance No. 1 P-T Limite Section 3.3.A(iv) of Oyster Creek Technical Specifications requires appropriate new pressure temperature limits be approved when the reactor  !

syste.n has reached 15 ef fective full power years (EFPY) of reactor j 1

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operation. Consric Lstter 88-11 also states.that licensees lare required

-to update _and fully implement new P-T curves within two plant outages-after the effective date (May-1988) of Revision 2 to Regulatory Guide

~1.99, " Radiation Embrittlement of Reactor Vessel Materials." Because of these requirements GPUN. letters dated July.26, 1989 and August 9, 1990 stated;that another set of P-T curves would-be submitted by the end of the upcoming 13R.

Neutron irradiation results in the embrittlement of pressure vessel steels. .The primary materials of concern are those surrounding the active core.- To monitor the effects of irradiation on these materials, test specimens fabricated from the materials used to. fabricate the reactor vessel are' installed on the reactor vessel wall at the core mid-plane. 'Dosiestry wires are included which provide an estimate of the fluence to which the specimens were exposed. The specimens and wires are periodically removed, tested, analyzed and the resulta evaluated to determine the extent of embrittlement as a function of fluence.

The property of concern is the reference nil-ductility temperature (RTNDT) which increases as a function of fluence and material chemistry. Once the RT NDT, fluence and material chemistry are known, predictions of:RTNDT in the future can be made. P-T curves are developed based upon the adjusted RTNDT at the end of the operating period.

After Cycle 9, CPUN removed Reactor Vessel-Materialo Surveillance Program (RVMSP) Capsule No.._-2. Its contents were tested and analyzed; the results were evaluated and. predictions of RT NDT for various periods of operation were prepared.

The new P-T limits were_ developed through 17 EFPY based upon the Reg.

Guide 1.99,'Rev. 2, methodology for predicting adjusted RTNDT'

-We have determined that this change request with respect to P-T limits involves no significant hazards considerations in that operation of the oyster Creek. Plant in accordance with the proposed amendment, will not:

1. Involve a significant increase in the probability of an accident because the new limits account for the increase in RTNDT' including: statistical uncertainty, due to neutron irradiation of the-reactor vessel as well as. establishing initial RTNDT on the basis of current code requirements, also including' statistical uncertainty, in accordance.with Reg._ Guide 1.99, Rev. 2. The new P-T curves.will assure that brittle fracture of the reactor vessel is prevented.

2. Create the probability of a new or different kind of accident from any accident previously evaluated. There now limits are the result of the calculation methodology in Reg. Guide 1.99, Rev. 2, as required by Generic Letter 88-11. Primary system' configuration and function remain unchanged.

3. Involve a significant reduction in margin of safety because the bases for the margin of_ safety remain the same as current limits, i.e., ASME, Sect. XI, App. G for available fracture toughness and applied stress intensity, Reg. Guide 1.99, Rev. 2 for calculating adjusted RT NDT, and 10 CFR 50, App. G, for criticality conditions.

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l I l chance No. 2 Boltuo Tempgrature- j The current'boltup temperature of 100'F is based on the assumption-that materials were qualified to meet 30 ft.-lb. Charpy energy at-

-I 40'F, based on the vessel purchase _ specification. The original code requirement was that the boltup be done at qualification temperature I (T30L) plus~60'F. Current Code requirements state,-in Paragraph 0-2222(c) of USNRC NUREG-0800, Standard Review Plan Section 5.3.2,

" Pressure-Temperature Limite" that for the application of full bolt.

preload and reactor pressure up to 20% of hydrostatic test pressure, the RPV metal temperature must be at RTNDT or greater. The approach used for Oyster Creek is to determine the highest value of (T3og + 60) by statistical data and the highest value of RTNDT both using a statistical analysis of the available Charpy data and base the boltup' temperature on the'more conservative value. This-evaluation shows a boltup temperature of 85'F. Alternatively, RT NDT is computed to equal 36'F so that a margin of 49'F exists.

We have determined that this' change request with respect to boltup temperature involves no significant hazards considerations in that Operation of the Oyster Creek Plant in accordance with-the proposed amendment, will not

1. Involve a significant increase in the' probability of an .

accident.because there is a significant margin over the current l

. code requirement. - The new value providea conservatism and more definitive technical basis.

2.- l Create the probability of a new or different. kind of accident

.from any accident previously evaluated. The calculation methodology for' determining the new limit is more conservative than the present Code requirement.- The system's configuration Land function remain unchanged.

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3. Involve a significant reduction in a margin of safety because the bases and methodology for developing the new limit are the same'as those for the current limits. The proposed limit has a significant margin over the current code requirement.

-S.O IMPLEMENTATION It is requestedLthat the amendment authorizing this change'become effective prior to restart of oyster Creek for the cycle 13 operation.

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