ML20134H039

Application for Amend to License DPR-16,requesting Deletion of Tech Spec Table 3.5.2 Which Lists Automatic Primary Containment Isolation Valves

ML20134H039
Person / Time
Site:	Oyster Creek
Issue date:	10/31/1996
From:	Roche M GENERAL PUBLIC UTILITIES CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20134H042	List: ML20134H039 ML20134H054
References
6730-96-2227, GL-91-08, GL-91-8, NUDOCS 9611130501
Download: ML20134H039 (9)

Text

=. - . _ - . . _ . ..

( GPU Nuclear. loc.

( U.S. Route #9 South NUCLEAR Post Office Box 388 Forked River, NJ 087310388 Tel 609-9714000 October 31,1996 6730-96-2227

)

i, U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 Technical Specification Change Request No. 205  ;

1 1

in accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request t

(TSCR) No. 205.

l This TSCR requests deletion of Technical Specification Table 3.5.2 which lists automatic primary l containment isolation valves. This request is in accordance with Generic Letter 91-08 which permits licensees to delete component lists such as Table 3.5.2. In addition, this TSCR clarifies the applicability of an action statement which applies to several limiting conditions for operation in Section 3.5 and deletes closure time requirements for several automatic isolation valves in ,

Section 4.5.F.  !

In accordance with 10 CFR 50.91 (b)(1), the designated oflicial of the State of New Jersey Bureau of Nuclear Engineering has been sent a copy of this TSCR.

)

130017 9611130501 961031 ._

PDR ADOCK 05000219

~

hblif/

P PDR

_ _ . _ _ _ - - ._ . . _ _ _ _ _ _ _ . _ _ . _. _ _ .~ . .-_ _ _

6730-96-2227 Page 2 Pursuant to 10 CFR 50.91(a)(1), enclosed is an analysis applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations. This license amendment application has undergone a safety review in accordance with Section 6.5 of the Oyster Creek l Technical Specifications and no unreviewed safety questions were identified.

Ifyou should have any questions concerning this license amendment application, please contact Mr. Paul F. Czaya at (201) 316-7975.

Very tmly yours, hY 0 ($ a Michael B. Roche Vice President and Director Oyster Creek PFC Attachments  ;

i c: Administrator, USNRC Region I l USNRC Resident inspector l Oyster Creek USNRC Project Manager

)

i  ;

1

,. y

. -= _. . _ - - -_- -

i 4

GPU Nuclear, Inc.

Oyster Creek Nuclear Generating FL-tion Facility License No. DPR-16 Technical Specification Change Request No. 205 Docket No. 50 219 Applicant hereby submits changes to pages 1.02,3.5-1 through 3.5-4, 3.5-8 through 3.5 12,4.5 2,4.5 3,4.5-11 and 4.5 12 and deletes page 3.5-13.  :

b By: Ltc Michael B. Roche l Vice President and Director Oyster Creek Sworn and Subscribed to before me this 3I day of October,1996.

EtruK LA -

A Notary Public of NJ -

GEMNE E. LEVIN 1 NOTARf PUBUC 0F MN gcommamanEM % *M  ;

-.. _~. . - . _ _ ~ .. . _ . .. . _ - - - - - . - - . . = , _ . _ . - . _ . . _ .

I ,

I I

GPU Nuclear,Inc. l U $ Route r9 South r g

NUCLEAR [,,7,,$',8 "fo'e'73i.o3,8 y  !

Tel 609 971-4000 6730-96-2227 October 31,1996 Mr. Kent Tosch, Director Bureau of Nuclear Engineering ,

Depanment of Environmental Protection  ;

CN 411 Trenton, NJ 08625 f

t i

Dear Mr. Tosch:

l

Subject:

Oyster Creek Nuclear Generating Station  :

Facility Operating License No. DPR-16  !

Technical Specification Change Request No. 205 i Pursuant to 10 CFR 50.91(b)(1), please find enclosed a copy of the subject document which was filed with the United States Nuclear Regulatory Commission on October 31,1996.

i Very truly yours, lhEc h bb4_

Michael B. Roche Vice President and Director Oyster Creek l Attachment I

i

I

? * .

1 1

l 1

GPU Nucleaf,inc.

l

' U S Route #9 South ,

'**'*"*** i NUCLEAR forked Rwer, NJ 087310388 '

Tel 609-9714000  ;

6730-96-2227  ;

i October 31,1996  ;

i The Honorable John Parker .

Mayor of Lacey Township i

818 West Lacey Road Forked River, NJ 08731

Dear Mayor Parker:

r 2

Enclosed herewith is one copy of Technical Specification Change Request No. 205 for the Oyster Creek Nuclear Generating Station Operating License. i This document was filed with the United States Nucicar Regulatory Commission on October 31 i l

1996.

Very truly yours, h #h Michael B. Roche Vice President and Director Oyster Creek Attachment i

l i

i

l .

I United States of America Nuclear Regulatory Commission i In the Matter of )

) Docket No. 50-219 j GPU Nuclear, Inc. )

CertificJte of Service  !

This is to certify that a copy of Technical Specification Change Request No. 205 for the Oyster .

Creek Nuclear Generating Station Operating License, filed with the U.S. Nuclear Regulatory Commission on October ,1996 has this day of October ,1996, been served on the Mayor of Lacey Township, Ocean County, New Jersey by deposit in the United States mail, addressed as follows:

The Honorable John Parker Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 i l

By: bbb Michael B. Roche '

Vice President and Director Oyster Creek 5

l l

1

l i

l Technical Specification Chance Reauest (TSCR) No. 205 1

I. Channes Reauested I GPU Nuclear requests that Appendix A Technical Specification pages be replaced as  !

follows:

Delete existing pages 1.0-2, 3.5-1 through 3.5-4,3.5-8 through 3.5-13,4.5-2,4.5-3,4.5- l 11 and 4.5-12 and replace them with attached revised pages 1.9-2, 3.5-1 through 3.5-4, l 3.5-8 through 3.5-12,4.5-2, 4.5-3,4.5-11 and 4.5-12.

II. Reasons for Channe Technical Specification Table 3.5.2 is a list of valves which receive automatic primary 1 containment isolation signals. Generic Letter (GL) 91-08 permits licensees to delete component lists such as Table 3.5.2 provided that cenain conditions are met.

Maximum stroke times for several automatic isolation valves are given in Specification l 4.5.F. As provided in GL 91-08 and the Improved Standard Technical Specifications (STS) NUREG-1433, stroke times for all but four of these valves can be deleted. The allowable closure time for the four main steam isolation valves is retained consistent with the STS An administrative change to an existing action statement is proposed. Specification 3.5.A.7 is several pages removed frcm the condition statements to which it applies. To enhance clarity, the action statement is being inserted into each of those condition statements and deleted as a stand alone specification.

III. Safety Evaluation Justifyinn Channe i Oyster Creek Technical Specifications describe conditions under which primary l containment shall be maintained and specific steps to be taken if one or more automatic primary containment isolation valves is inoperable. In addition, the Technical Specifications require testing for automatic closure by isolation signal, post-maintenance ;

operability testing, leak rate testing and specific closure times for particular valves.

1 Technical Specification Table 3.5.2 lists automatic primary containment isolation valves and describes the primary containment isolation signals they receive. The proposed deletion of Table 3.5.2 does not alter or reduce Technical Specification requirements but shifts identification of automatic primary containment isolation valves from Technical Specifications to controlled plant procedures. In addition, references to Table 3.5.2 have l been deleted from the text and replaced by a description of the subject valves in l

l 1

l

i I

Specifications 3.5.A.3.a. 4.5.F.1,4.5.F.2 and in Defmition 1.13. These changes conform to the guidance contained in GL 91-08.

Valve stroke times are given in Specification 4.5.F.1 for main steam line, isolation condenser, cleanup, cleanup auxiliary pumps and shutdown cooling isolation valves. The proposed deletion of closure times for automatic primary containment isolation valves (except main steam line isolation valves) in Specification 4.5.F.1 does not remove the closure time test requirement which is retained in Specification 4.5.F.2. The isolation condenser isolation valves do not receive a primary containment isolation signal (the isolation condenser vent valves do, however). The isolation condenser isolation valves close on line break signals and are required to be tested in accordance with Specifications 4.8. A.1 and 2 which are not changed. Closure time limits are incorporated in controlled plant procedures. These time limits ensure design basis performance objectives are met as described in Technical Specification bases. The deletion of automatic primary containment isolation valve closure times is consistent with the guidance in GL 91-08 in  !

that the closure time testing requirement remains in Specification 4.5.F.2 for automatic primary containment isolation valves and the inservice testing program required by Specification 4.3.C covers stroke time verification testing for these valves.

Specification 3.5. A.7 is an action statement which requires that a shutdown be initia:ed and the plant be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if Specifications 3.5.A.l.a, b, c(1) and 3.5.A.? through 3.5.A.5 cannot be met. The action required by Specification 3.5.A.7 has been inserted into Specifications 3.5.A.1 (as 3.5.A. l .d), 3.5. A.3

[as 3.5.A.3.a(2)] and 3.5.A.5 (as 3.5.A.5.d). Specification 3.5.A.2 establishes conditions to be satisfied before pressure suppression system maintenance and repair work can be performed. 'liese conditions require the plant to be in the same condition as Specification  ;

3.5.A.7 (cold sbutdown). Therefore, the requirements of Specification 3.5.A.7 are i redundant and it is unnecessary to insert the action statement into Specification 3.5.A.2.  ;

A previous license amendment had inserted the action statement into Specification 3.5. A.4 (as 3.5. A.4.c) and additional change is not required. This change does not modify the  !

limiting conditions for operation nor the required action to be taken if those conditions are not met.

Technical Specification Definitions on pages associated with this TSCR are capitalized consistent with STS. Page 3.5-13 which contains Table 3.5.2 should be deleted as well as the existing page which contains Table 3.5.1. Table 3.5.1 was deleted by a previous license amendment.

Technical Specification bases have been revised to provide greater clarity regarding primary containment isolation valve design bases. The changes appear on pages 3.5-9, 4.5-11 and 4.5-12. For pagination purposes all Section 3.5 bases pages should be reissued. Amendment numbers at the bottom of each bases page have been revised to 2

4 1 reflect repagination and to reflect amendments which revised bases and not simply denoted previous repagination.

IV. No Sinnificant Hazards Consideration GPU Nuclear has determined that this TSCR poses no significant hazards as defined by the NRC in 10 CFR 50.92. <

l. The proposed deletion of the automatic primary containment isolation valve Table 3.5.2 and closure times for several valves in Specification 4.5.F.1 are administrative in nature and do not afreet the purpose, function, operability and testing requirements of the automatic primary containment isolation valves or the isolation condenser isolation valves. The required action contained in Specification 3.5.A.7 has been moved to the associated specifications and has not changed. Capitalizing definitions and deleting unneeded pages are also administrative changes which enhance the usability of the Technical Specifications. i Therefore, the proposed changes do not increase the probability of occurrence or consequence of an accident previously evaluated.

2. The proposed changes are administrative and do not involve a physical change to plant configuration nor do they affect the performance of any equipment. Existing limiting conditions for operation and surveillance requirements are retained, i Therefore, the possibility of a new or different kind of accident from any accident I previously evaluated is not created. l

3. Deleting the list of valves in Table 3.5.2 and valve closure times in Specification l

4.5.F.1 are administrative changes which do not affect the purpose or function of the automatic primary containment isolation valves. The listing of the automatic primary containment isolation valves and stroke time requirements will be in controlled plant procedures. Changes to the list or closure times can be made in accordance with review procedures required by Section 6.5 of the Technical Specifications and 10 CFR 50.59. Similarly, inserting the statement of required action in Specification 3.5 A.7 into the Specifications to which it applies does not modify the condition or the action to be taken and is an administrative change which clarifies the Technical Specifications. Therefore, the margin of safety is not  !

reduced.

V. Imolementation It is requested that the license amendment authorizing the proposed changes be effective j

60 days after issuance to permit required procedure changes to be implemented.

1 4

3 l

l