ML20148J307

Submits Proposed Change 149 to Tech Specs,Modifying Surveillance Testing on Personnel Hatch,Electrical Penetrations & Containment Isolation Valves

ML20148J307
Person / Time
Site:	Yankee Rowe
Issue date:	03/09/1977
From:	Vandenburgh D YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20148J312	List: ML20148J307 ML20148J325
References
WYR-77-27, NUDOCS 8011210681
Download: ML20148J307 (3)

Text

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, F Proposed Change No.149

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As-r\ 11Co,/JCb v, /j March 9, 1977

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d1 l'nited States "uclear Regulatory Connission Lashington, 3. C. 20555

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0 4 @o Attention: Office of Huclear Reactor Regulation 4 i A0 s/

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References:

1. License No. DPR-3 (Docket No. 50-29)

2. Letter A. Schuencer to YAEC, dated 11/29/76 ,

3. Letter YAEC to A. Schuencer, dated 2/7/77

Dear Sir:

Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yanhec Atomic Electric Company hereby proposes the follouing nodifications to Appendix A of the Operating, License.

PMpOSCD C:IA"GE: Reference is nade to the Operating Licence No. DPR-3 issued to Yankee Atonic Electric Company for the Yanhec Roue plant.

Uc propose to amend the license as follous: P.cplace the existing specifications 4. 6.1. :', 4.6.1. 3 and 4.6. 2.1 and their associated bases uith the corresponding reviscJ specifications attached. For the purposes of revicu, the pages affccted in the present Technical Specificctions are: 3/4 fi-3, 3/4 6-4, 3/4 6-12, 3/4 6-13, 3/4 6-14, 3/4 6-15, 1 3/4 6-1, 3 3/4 6-2, 9 3/4 f-3. i Yhese changes nodify the surveillance t ec ti no, on tSe personnel hatch, the electrical penetrations an! the containnent isolation valves.

i T* MON Pon C"'"7: The purpose of this change in to bring the Yankee iove plant into compliance with Appendix J to 10CTR Part 50 as ca supplemented by the specific exemptions proposed by 'F'.C in i'eference E ,.,

(2). In accordance with 10Cr?. Part 50.12 justification for these NW c

specific exenptions was provided in Reference (3). The follouing is

• an explanation of the chanc,cs requested to acet the requirenents of af

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Appendit J.

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Pronosed Soccification 4.6.1.2.e - This specification deals uith the WW

$g surveillance testing of electrical penetration to the containnent. 8 Due to the ar uous nature of leah testing these pentrations, an d

o c' extension to the tuo year testing interval specified in paragraph 92 2 III.S.2 of Appendix J has been requested. Per this proposed cpecification Yanhoe vould leah test annually at least 25 percent of $

the electrical penetrations. Additionally, any penetration uhich failed the annual test vould be rotested during the follouin; intervals until tuo acceptabic leah tests had been denonstrated.

80112.10 g/ M

. United States Mucle " Regulatory ConSission 5 March 9, 1977 Attentiont Office of Nuclear Reactor Regulation Page 2 Also, any penetration being rctested would not be included as part of the 25 percent selected for the annual test. ,

- Proposed Specification 4.6.1. 3.a - This specification delineates the surveillance intervals for the containnent personnel hatch air lock.

Appendix J Section III.D.2 requires testing of the containnent air loch seals once per 6 months or if the door is opened; af ter each opening. Yankee is presently in confornance with Appendix J uith regards to the 6 month tests. Due to the significant amount of time required for the internediate tests, however, Yanhec vishes to take advantage of the exemption for airlock testing provided by MRC in Reference (2). This exemption provides ' for leak tes ting of the air loch door seals within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the first of a series of openings.

Thus if the air lock door was opened during the interval between the 6 nonth tests,. no longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> would clapse from the tino of the opening until the seals ucre leak tested.

As uns stated in Reference (2), URC regards this position as an acceptable alternative for satisfying the objectives of the air lock testing requirements of Appendix J.

Proposed Table 3.6 This table lists containnent isolation valves, both autonatic and nanual, which nust be naintained OPERA 3LE via the surveillance of specification 3.6.2. Section i of proposed Tabic 3.6-1 lists those lines containing automatic isolation valves. Valves uhich ucre previously listed in Section A as "Not subject to Type C )

Tests" are located in the secondary stean systen of a pressurized water reactor, whereas Appendix J specifically address these valves as being isolation valves for direct cycle boiling vater reactors only. l Uc are therefore requesting that these valves be renoved frn, Section l A of Tabic 3.6-1. All valves in Section A of the proponed table shall l neet the testing requirements of Appendix J.

Chech valves have been elininated f ron the proposed Tabic 3.5-1.

All lines containing check valves are ' coning lines to the vapor container. These lines are either -c .d filled at a pressure in excess of the calculated seal accident cont ainnent pressure or from closed loop., both inside and outside of the containncat. These check valves are systen isolation valves designed to limit transients in such systens as the component cooling systen and not to provide isolation of these lines. He are requesting that these valves be renoved fron the list of containment isolation valves and thus not be subject to Type C Testing.

Section B of the proposed Table 3.6-1 lists ,anual valves in lines ponctrating the containment. Reference (3) contains the justifications for exempting certain of these manual valves fron Type C Testing. All valves listed in the proposed Table 3.6-1 shall be tested in accordance with the requirenents of Appendix J.

The last section of the present Table 3.6-1 lists itens which Yankee feels do not qualify an isolation valves. These are such itens as hatches and electrical ponctrations which are addressed elseuhcre in the Technical Specifications. I'or this reason we are requestin",that

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United St,ates Uuclear Regulatory Connission i

.fiarch 9, 1977  !

Attention: 20/fice of.11uclear Reactor Regulation Page-3 4

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these iteds be dropped f ron the list of' containnent isolation valves as this.is'not the intent nor the scope of Table 3.6-1. l SATETY CONSIDERATIONS: This proposed change would bring the Yankee  !

Rove plant into conformance with the requirements of Appendix ~J with '

. specific exenptions. This change has boon carefully evaluated and

' does not' change the intent nor. alter the bases f or any Technical l Specifications. Based on the proceding argunents, we conclude that l this change'does not endanger the health and safety of the public.

This change has been reviewed by the Nuclear Safety Audit and McView

. Connittee.

SCHEDULE E CHAMCC: Yankee Rouc Technical Specifications will bc changed and the changes inplenented prior to startup following the'

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sunner of 1977 refueling subject to Connission approval.

He trust that you will find this infornation satisfactory; however, should you desire additional infornation, please contact us.

1 Very truly yours, 1 YAMKEE ATO?IIC ELECTRIC COMPANY t

l D. E. Vandenburgh  !

Senior Vice President I l

Co.nonwealth of 'fassachusetts) l

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County of Ucrcester )  !

Then personally appeared before ne, Donald E. Vandenburgh, uho bein3 duly cuorn, did state that he in a " ice Drcofient of Yanhec Atomic l

Elect ric Company and that he is duly authorized to e::ecute and file the I fore"oing anendnent in the nanc and on the Schalf of Yankee Atomic Electric Company, and that the statenents in said ancadnent are true to the best of his knowled;c and belief.

PT ~

Arnand P. Soucy Notary Public My Connission ib:pires September 9,1977