ML19209C054
| ML19209C054 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 10/05/1979 |
| From: | Vandenburgr D VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| WVY-79-113, NUDOCS 7910110442 | |
| Download: ML19209C054 (5) | |
Text
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Proposed Change No. 84
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V EIO10NT Y AN K EM NUCLEAR POWER COR POR ATION t
SEVENTY SEVEN GROVE STREET B.3 2.1 l(UTI.AND, YEf t >10NT 05701 g,
REPLY TO.
ENGINEERING OFFICE TURNPIKE RO AD WESTDORO, M ASS ACHUSETTo 01581 October 5, 1979 TELEPHONE 617-366-9011 United States Nuclear Regulatory Commission Washington, D.C.
20555 Attention: Office of Nuclear Reactor Regulation T. A. Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors
Reference:
(a) License No. DFR-28 (Docket No. 50-271)
(b) VYNPC Letter (WVY 79-79) to USNRC dated July 5, 1979
Dear Sir:
Subject:
Control Rod Hydraulic Return Line Isolation Valves Pursuant to Section 50.59 of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation hereby proposes the following modifications to Appendix A of the Operating License.
2ROPOSED CHANGE:
Delete " Control Rod Hydraulic Return Check Valves" V3-llo and V3-113 from Technical Specification Table 4.7.2.b.
Add valve V3-181 to Technical Specification Table 4.7.2.a.
REASON FOR CHANGE:
In order to eliminate the possibility of cracking in the control rod return line nozzle area and the necessity for future nozzle inspections, a design change will be implemented at Vermont Yankee during the 1979 refueling outage as described in Reference (b). This design change involves the cutting and capping of the control rod hydraulic returnline RPV nozzle and rerouting of the retura line flow to the Reactor Water Cleanup (RWCU) system.
Valves V3-110 and V3-113 will be eliminated from the control rod drive system design and, as such, can be deleted from the Technical Specification. Check valve (V3-181) will be added to the new control rod hydraulic return line to prevent backflow and to provide a primary containment isolation function.
To be consistant with isolation criteria applied to other valves, (i.e. V12-68) used in similar applications this valve will be subject to periodic Appendix J, Type C leakage tests.
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United States Nuclear Regulatory Commission October 5, 1979 Attention: Office of Nuclear Reactor Regulation Page 2 SAFETY CONSIDERATIONS:
The design change alluded to above, including nozzle capping and line re-routing has been developed, and will be implemented, in accordance with our NRC approved quality assurance program.
An evaluation of the change has been made and it has been concluded that the change does not present significant hazards not described or implicit in the safety analysis report and does not involve an unreviewed safety question as described in 10CFR50.59.
The deletion of valves V3-110 and V3-113 from the Technical Specification is therfore administrative in nature and is proposed only to assure th.t Table 4.7.2 is up-to-date.
The inclusion of check valve V3-181 into Table 4.7 2.a and the requirement to perform periodic leakage tests will assure that valve leakage will be kept within allowable values as defined in the Technical Specification.
This change has been reviewed by the Vermont Yankee Nuclear Safety and Aud!t Review Committee.
FEE DETERMINATION:
This proposed change is proforma, administrative in nature, and has no safety or environmental gnificance. For these reasons Vermont Yankee Nuclear Power Corporation proposes this change as a Class II Amendment and a payment of $1,200.00 is enclosed.
Vermont Yankee believes that the NRC revised fee schedule is illegal. We are aware that an appeal of the decision of the U.S. Court of Appeals for the Fifth Circuit is being considered and therefore submit the enclosed fee under protest without waiving its right to contest the validity of the fee or the entire NRC fee schedule, and without waiving any right to recover, in whole or in part, all fees paid or to be paid under the invalid fee schedule.
SCHEDULE OF CHANGE:
The control rod hydraulic return line re-routing and RPV nozzle capping is expected to be completed by October 15, 1979 The revised pages will be incorporated into the Technical Specification upon receipt of NRC approval.
We trust this submittal is acceptable to you; however, should you have any questions, please contact us.
Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION D. E. Vandenburgh Vice President dep j] 2h4 Enclasure
United States Nuclear Regulatory Commission October 5, 1979 Atter3 tion: Office of Nuclear Reactor Regulation Page 3 COMMONWELATH OF MASSACHUSETTS) )ss. C* NTY OF WORCESTER ) W Then personally appeared before me, D. E. Vandenburgh, who, being duly sworn, did state that he is Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.
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Robert H. Groce Notary Puolic d #,' *,
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TABLE 4.7.2.a PR1HARY CONTAltafENT ISOLATION VALVES val.VI:S SilBJi:CT 10 TYPE C 1.EAKAGE TESTS Ilumber of Power Maximum Action on Isolation Operated Valves Operating Normal Ini t iatin;; Coinp (!!ot e 1) Valve Identification Inboa rd Outboard Time (sec) Position Slynal 1 Itain Steam Line Isolation (2-60a, D & 2-86A, D) 4 4 5(note 2)' Open CC 1 tlain Steam 1.ine Drain (2-74, 2-77) 1 1 35 Closed SC 1 Itecirculation Loop Sample Line (2-39, 2-40) 1 1 5 Closed SC 2 lutR Discharge to Raduaste (10-57,10-66) 2 25 Closed SC 2 Dryuell Floor Drain (20-112, 20-83) 2 20 Open CC 2 Dryuell Equipment Drain (20-94, 20-95) 2 20 Open CC 3 Dayuell Air P..rne Inlet (16-19-9) 1 10 Closed SC 1 Dayuell Air Purne Inlet (16-19-H) 1 10 Open CC 1 la yuel l l'urne & Vent Outlet (16-19-7A) 1 10 Closed SC 3 D:yuel1 Purne & Vent Outlet Hypass (16-19-6A) 1 10 Closed SC 3 Dryuell 6 Suppression Chamber liain Exhaust (16-19-7) 1 10 Closed SC 3 Suppression Chamber Purge Supply (16-19-10) 1 10 Closed SC 3 Suppression Chamber Purge 6 Vent Outlet (16 7 B) 1 10 Closed SC 3 Suppression Chamber Purge & Vent Outlet Bypass (16-19-6B) 1 10 Open CC 3 Exhaust to Standby Cas Treatment System (16-19-6) 1 10 Open CC 3 Contalument Purge Supply (16-19-23) 1 10 Open CC 3 Cuntainment Purne Makeup (16-20-20, 16-20-22 A, 16-20-22 B) 3 NA Closed SC 5 1:cactor Cleanup System (12-15,12-18) 1 1 25 open CC 5 l<eaci nr Cleanup System (12-68) 'l 45 Open CC 6 IIPCI (23-15, 23-16) 1 1 55 Open CC 6 1:Cic (13-15, 13-16) 1 1 20 Open CC Primary / Secondary Vacuum Relief (16-19-11A, 16-19-11B) 2 tIA Closed SC Primary / Secondary Vacuum Relief (16-19-12A, 16-19-12B) 2 t!A Closed Process Control Rod Ilydraulic Return Check Valve (3-181) NA Open Process j p@ lb a N 135. CB
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Table 4.7.2.b PRIMARY CONT \\IDENT ISOLATION VALVES _ VALVES NOT SUBJECT TO 'IPE C LEAKAr.E TESTS Nurber of Pcwcr Maximum Action en Isolation Operated Valves Operating Norval Initiating Group (Note 1) Valve Identification Inboard Outboard _ Tim (sec) Pesition Simal 2 -R!!R Return to Suppres.) ion Pool '30-39A, B) - 2 70 Clos ed SC 2 RllR Return to Suppression Pool (10-34A, B) 2 120 Closed SC 2 R!lR Drmell Spray (10-26A, B & 10-31A, B) 4 70 Closed SC 2 RilR Suppressien Chanber Spray (10-3SA, B) 2 45 Closed SC 3 Containmnt Air Coi pressor Suction (72-38A, B) 2 20 Open GC 3 .Containecnt Air So pling Systera (109-75A, D; 1, 2109-76A, B) 10 5 Open CC 4 RIIR Shutdcun Cooling Supply (10-18,10-17) 1 1 28 Closed SC 4 RilR Reactor !! cad Cooling (10-32,10-33) 1 1 25 C1csed SC Eacduater Check Valves (2-28 A, B) 2 2 NA Open Proces Reactor Head Cooling Check Valve (10-29) 1. NA C1csed Procc: Standby Liquid Control Check Valves (11-16, 11-17) 1 1 NA Closed Proces _- a ['
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