View source for BVY-90-122, Submits 30-day Response to Suppl 3 to Generic Ltr 89-10, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves. Plant Design Does Not Include Isolation Condenser

{{Adams
| number = ML20065S260
| issue date = 12/14/1990
| title = Submits 30-day Response to Suppl 3 to Generic Ltr 89-10, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves. Plant Design Does Not Include Isolation Condenser
| author name = Pelletier J
| author affiliation = VERMONT YANKEE NUCLEAR POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000271
| license number = 
| contact person = 
| document report number = BVY-90-122, GL-89-10, NUDOCS 9012200182
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 2
}}

=Text=
{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _                     --
VERMONT YANKEB
,     NUCLEAR POWER CORPORATION
        *y               Ferry Road. Brattleboro. VT 05301 7002                                                BVY 90-122 h        kf-)
ENGINE If G OFFICE LR0 V AiN $tRE f i
                ,                                                                                            ICLTON MA 0174D SD!o 74-(.711 December 14, 1990 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

==References:==
: a.       License No. DPR 28 (Docket No. 50 271)
: b.       Letter, USNRC to [Atl Licensees), NW 85 250, dated November 15, 1985 (Bulletin 85 03)
: c.       Letter, WNPC to USNRC, BW 89 050, dated June 8,1989
: d.       Letter, USNRC- to [All Licensees), NW 89144, dated June 28, 1989 (Generic Letter 8910)
: e.       Letter, WNPC to USNRC, BW 89-116, dated December 28,1989
: f.       Letter, USNRC to WNPC, NW 90109, dated June 11, 1990                                           i
: g.       Letter, USNRC to [All Licensees). NW 90-123, dated June 13, 1990                               l (Supplement to Generic Letter 8910)
: h.       Letter, USNRC to [All Licensees), NW 90148, dated August 3,1990 (Supplement 2 to Generic Letter 8910)
: 1.       Letter, USNRC to [All Licensees), NW 90198, dated October 25, 1990 (Supplement 3 to Generic Letter 8910) l l          

==Subject:==
Thirty Day Response to Generic Letter 8910, Supplement 3. " Consideration l                           of the Results of NRC Sponsored Tests of Motor Operated Valves"

==Dear Str:==

In Supplement 3 to Generic Letter 8910 [ Reference (I)), Reporting Requirement No.1, NRC requested BWR licensees to notify NRC staff, within 30 days of letter receipt, that a plant.
specific safety assessment report addressing, as a minimum, the factors described in Reference L          (I), be made available on site for staff review. Further, BWR licensees were requested to notify I
the .NRC staff whether they believe that there are MOV's with deficiencies of greater safety significance than the MOV's used to provide containment isolation in the steam supply lines of the HPCI and RC!C systems, in the supply line of the RWCU system, and in the line to the isolation condenser. The purpose of this letter is to provide the information -requested by Reporting Requirements No.1. Reference (I) was received by Vermont Yankee on November 14, l          1990.
Vermont Yankee has prepared a plant specific safety assessment which addresses the ,
factors described in Reference (1). This safety assessment is available at the Vermont Yankee plant site.
Vermont Yankee has performed a review of the HPCI steam supply isolation valves, the RCIC steam supply isolation valves, the RWCU supply isolation valves, and the Recirculation Loop pump discharge valves. This review concluded that these valves have no safety significant deficiencies and are capable of closing under design basis accident conditions. Further, l

F. ,   .
VERMONT YANK                                     NUCLE AR POWER CORPOR ATION United States Nuclear Regulatory Commission December 14, 1990 Page 2 Vermont Yankee does not believe there P.ro other MOV's at Vermont Yankee with safety-significant deficiencies. A safety significant deficiency is defined as a deficiency that would prevent a valve from performing its required safety function. Vermont Yankee's design does not include an isolation condenser.
We trust that this Information is responsive to your request; however, should you have additional questions or require additional information, please contact this office.
Very truly yours, Vermont Yankee Nucient Power Corporation mWC eV V s Q' [ * %
ames P. Pelletier Vice President, Engineering ec:        USNRC Region 1 Administrator USNRC Resident inspector VYNPS USNRC Project Manager VYNPS STATE OF VERMONT)
                                                          )ss WINDHAM COUNTY )
Then personally appeared before me, James P. Pelletier, who, b6;ng duly sworn, did state that he is Vice President, Engineering of Vermont Yankee Nuclear Power Corporation, that he is duty authorized to execute and file the foregoing document 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.
f wlY                   Y-       0 Diane M. McCue                           Notary Public
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