ML19257D114

Tech Spec Change Request 80 Re Tech Specs 3.5.A.9 to Reflect Reduction in Min Suppression Chamber Downcomer Submergence Level.Certificate of Svc Encl

ML19257D114
Person / Time
Site:	Oyster Creek
Issue date:	01/29/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19257D111	List: ML19257D110 ML19257D114
References
NUDOCS 8002010335
Download: ML19257D114 (6)

Text

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JERSEY ChtlTRM., PCWER & LIGliT CCriPANY OYSTER CREEK NUCLEAR GENERATI!JG STATIG1 PROVISIGlAL OPEPATING LICENSE NO. DPR-16 Technical Specitication Change Request No. 80 Docket No. 50-219 Applicant subraits, by illis Technical Specification Ctlange Recuest No. 80 to the Oyster Creek Nuclear Generating Station Technical Specifications, cilanges to Specification 3.5.A.9.

JERSEY CENTRAL PWER & LIGill' CC11PANY EY: ,

j Vice Presiden

[

STATE OF NEW JLPSEY COU:71'Y OF MORRIS Sworn and subscribed to before me tnic /' ' ' clay of ' , , , 1980.

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Notary Public rR '/ .. '_ .1 ' a:5 t;ortry,J. >: c:.. / ):UEY My Coe rc.ss'an L e , Aug,16,19 8 4-1855 182 soon oio 33C

UNITED STATES OF AMERICA NUCLEAR REGULYIORY CQelISSION IN THE FATTER OF )

) Docket Number 50-219 JERSLY CENTRAL PChult & LIGHT COiPLY )

CERTIFICATL OF SERVICE

'1his is to certify that a copy of Technical Specification Change Request No. 80 for tne Oyster Creek Nuclcar Generating Station Technical Specifications, filed with the U.S. Nuclear Regulatory Comission on January 29 ,1980, nas this 29th day of January,1980, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail addressed as follows:

Tne Honorable Henry Von Spreckelsen Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08731 JERSEY CEtERAL POWER & LIGHT CCF@ANY BY: 4%w p Vice Presi t [

DATED: January 29 , 1980 1855 183

Jersey Central Power & Ught Company N2 "

Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 (201)455-8200 January 29, 1980 Tne Honorable Henry Von Spreckelsen Mayor of Lacey Township P. O. Box 475 Forked River, New Jersey 08731

Dear Mayor Von Spreckelsen:

Enclosed herewith is one copy of Technical Specification Change Request No. 80 for the Oyster Creek Nuclear Generating Station Technical Specifications.

Tnese documents were filed with tne U. S. Nuclear Regulatory Commission on January 29 , 1980.

Very truly yours, M -

Ivan R. Finfroc' Jr.

Vice President la Enclosures 1855 184 Jersey Central Power & Light Company is a Member of the General Pubhc Utihties System

JERSEY CENTRAL POWER 6 LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION (DOCKET NO. 50-219)

PROVISIONAL OPERATING LICENSE DPR-16 App)icant hereby requests the Commission to change Appendix A to the above captioned license as follows:

1. Section to be changed:

Section 3.5.A.9

2. Extent of Change:

Revise the above section such that a suppression chamber downcomer submergence range of 3.0 to 5.3 feet is acceptable.

3. Change requested:

The requested change is on the attached revised Technical Specification pages 3.S-7 and 3.5-14.

4. Discussion:

This Technical Specification change is a result of the bhrk I Containment Long Term Program as presented in General Electric's Report "NEDE-21885-P, hhrk I Downcomer Reduced Submergence - Functional Assessment Report." The report was forwarded to the Nuclear Regulatory Commission by General Electric on July 31, 1978.

In order to mitigate the pool swell loads in the torus as a result of a LOCA, the downcomers in the torus shall be truncated such that there is a three foot submergence below the minimum allowable suppression pool water level.

General Electric's Report NEDE-21885 0 presents the technical basis for the use of three feet minimum downcomer submergence in Mark I plants, via truncation of the existing downcomer length, and indicates that such a modification will not prevent the containment from performing its intended safety function.

iliS5185

3.5-7 containment is required during fuel handling operations and whenewr work is being performed on the reactor or its connected systems in the reactor building since their operation could result in inadvertent release of radioactive material.

The standby gas treatment system (6) filters and exhausts the reactor building atmosphere to the stack during secondary containment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs.

Two separeg filter trains are train provided eachinoperable, having 100%

capacity. If one filte- becomes 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 on considerations presented in the Bases in Specification 3.2 for a one-out-of-two system.

References:

(1) FDSAR, Volume I, Section V-1 (2) FDSAR, Volume I, Section 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) Licensing Application, Amendment 32, Question 3 (9) Robbins, C. H., " Tests on a Full Scale 1/48 Segment of the Humboldt Bay Pressure Suppression Containment,"

GEAP-3596, November 17, 1960.

(10) Bodega Bay Preliminary Hazards Summary Report, Appendix 1, 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 unique analysis was performed on August 2, 1976, which demonstrated a factor of safety of at least two for the weakest element in the suppression chamber support system. The maintenance of a drywell-suppression chamber differential pressure within the range shown. on Figure 3.5-1 with a suppression chamber water level corresponding to a downcomer mJamergence range of 3.0 to 5.3 feet will assure the integrity of the suppression chamber when subjected to post-LOCA suppression pool hydrodynamic forces.

~

1855 186 Amendment No.

3.5 -14 REQUIRED DRYWELL TO TORUS DIFFERENTIAL PRESSURE l.4 -

lis n.

tai g 1.3 -

ACCEPTABLE m OPERATING l0 RANGE E

si 5 1.2 -

td M

td l.1 O

y a

d a>-

E o 1.0 -

O.o . . . . . . . . . . . .

3.0 3.4 3.8 4.2 4.6 5.0 . 5.4 1855 187 DOWNCOMER SUBMERGENCE, FT.

FIGURE 3.5-I

• The actual acceptable range of downcomer submergence is governed by the Technical Specifications limit on maximum and minimum water 'colume in the torus (see section 3.5.A.1). This actual acceptable range of downcomer submergence will not encompass the full range of downcomer submergence indicated in the figure above.

AMENDMENT NO.