ML20151M782

Forwards Rev 9 to Inservice Testing Program,Vermont Yankee, Including Description,Program,Testing Schedules & Relief Requests,Per 10CFR50.55a(g)(5).Rev Necessary to Incorporate Commitments Made in .Fee Paid

ML20151M782
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	07/28/1988
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20151M786	List: ML20151M782 ML20151M789
References
FVY-88-63, NUDOCS 8808080003
Download: ML20151M782 (4)

Text

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VERMONT YANKEE NUCLEAR POWER CORPORATION FVY 88-63 RD 5, Box 169, Ferry Road, Brattleboro, VT 05301

,,, yo ENGINEERING OFFICE Li 1671 WORCESTER ROAD FRAMING H AM, MASS ACHUSETTS 01701 TE "_ PHONE 4t? 672-8100 July 28, 1988 U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Attn:

Document Control Desk

References:

a)

License No. OPR-28 (Docket No. 50-271) b)

Code of c deral Regulations, Title 10 Chapter 1, Part 50, e

Section 50.55a(g) c) ASME Section XI, 1980 Edition through the Winter 1980 Addenda d)

Letter, Mr. V.L. Rooney, USNRC, to Mr. R.W. Capstick, VYNPP,

Subject:

Request for Additional Information - IST Program,"

Docket 50-271, NVY 87-01, dated January 5, 1987 e)

Letter, Mr. V.L. Rooney, USNRC, to Mr. R.W. Capstick, VYNPC,

Subject:

Meeting Summary," Docket 50-271, NVY 88-074, dated May 9, 1988 Dear Si.-

Subject:

Inservice Testing Program, Revision 9 As required by 10CFR50.55a(g)(5), we are submitting herewith information responding to Reference e).

Revision of this testing program is necessary to incorporate commitments made in Reference e) and to include pump and valve testing improvements developed by both Vermont Yankee and the ASME Section XI Code.

Further identification and description of specific changes are pro-vided in Attachment 1.

This revised program has been developed in accor-dance with Reference b) to meet the requirements of Reference c).

Implementation of this revised program is in progress.

In accordance x,th the provisions of 10CFR170.12, and application fee of

$150 is enclosed.

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VERMONT YANKEE NUCLEAR POWER CORPORATION U.S. Nuclear Regulatory Commission July 28, 1988 Page 2 We trust that the information contained in this submittal is satisfactory; however, should you have any questions or require additional information, please contact us.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION g

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Warren P.

urphy Vice Pre ident and Manager of Operations Attachments

/ss cc: USNRC Regional Administrator, Region I USNRC Resident Inspector, VYNPC USNRC Mr. V.L. Rooney USNRC Mr. D.L. Caphton 4

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ATTACHMENT 1 1.

The program presented within this document was written to comply with the requirements of 10CFR50.55a(g) concerning inservice testing, evaluation, and repair of sefety-related pumps and valves.

2.

This program incor porates extensive changes that are a result of meetings between the NRC and Vermont Yankee Nuclear Power Corporation (VYNPC) on October 14 and 15, 1987 (Reference e).

All issues resolved at that meeting have been included.

In addition, a number of open items con-cerning valve testing were identified.

VYNPC resolution of these items is summar,zeJ as follows:

a) Questions V-11.2, V17 & 18.3, and Vi7 & 18.9 concern testing of valvas that provide a burrie-betweer nigh and low pressure piping.

The valves in question have all besr :esignated as Category A or A/C.

The VYNPC position on testing cf these valves is included in Relief Request Basis V-14 and V-22.

b) Questions V12-14.8 and V19-21.7 concern the omission of check valves j

in HPCI and RCIC auxiliary systems frol, the program.

The four valves in questian have all been added to the program and will be appropriately tested.

c) Leak testing of Standby Liquid Control check valves is addressed by question V-16.2.

The two valves in question will be leak tested per the requirements of IWV-3420 with conditions given in Relief Request Basis V20.

d) Questions V-7.8 and V-17 & 18.1.b address compliance with IWV-3426 and IWV-3427, Analysis of Leakage Rates and Corrective Action.

The VYNPC resolution of this issue is included in Relief Request Basis GV-3.

3.

Additional changes included in this program revision are as follows:

a) Pump vibration testing will now be performed in accordance with ANSI /ASME Draft Standard OM-6, "Inservice testing of Pumps", Draft 11, as noted in Relief Request Basis GP-3.

b) Relief Request Rasis GV-2 has been added which changes the 6 teeptance criteria :nd corrective actions for valve stroke time testing.

The revised cr:teria and actions are consistent with ANSI /ASME Draft Standard OH-10, "Inservice Testing of Valves", Draft 11.

A.

Reference e), Pump Question 2, addressed testing of the HPCI glana Seal Exhauster and HPCI Hot Well Condensate Pump. VYNPC response to this item in the October, 1987 meeting with NRC identified these two pieces of equipment as non-safety related ano therefore not included in the program.

This equipment has recently been upgraded to Safety Class 3.

Proper operation of this equipment will be demonstrated by acceptable operttion of the HPCI sys*em during normal surveillance testing.

We continue with our position t

t these pumps are part of the HPCI SKID and therefore need not be designated specifically in this program.

e ATTACHMENT 1 1

l l

1.

The program presented within this document was written to comply with the l

requirements of 10CFR50.55a(g) concerning inservice testing, evaluation, and repair of safety-related pumps and valves.

2.

This program incorporates extensive changes that are a result of meetings between the NRC and Vermont Yankee Nuclear Power Corporation (VYNPC) on October 14 and 15, 1987 (Reference e).

All issues resolved at that meeting have been included.

In addition, a number of open items con-cerning valve testing were identified.

VYNPC resolution'of these items is summarized as follows:

a) Questions V-11.2, V17 & 18.3, and V17 & 18.9 concern testing of valves that provide a barrier between high and low pressure piping.

The valves in question have all been designated as Category A or A/C.

The VYNPC position on testing of these valves is included in Relief Request Sasis V-14 and V-22.

b) Questions V12-14.8 and V19-21.7 concern the omission of check valves in HPCI and RCIC auxiliary systems from the program.

The four valves in question have all been added to the program and will be appropriately tested.

c)

Leak testing of Standby Liquid Control check valves is addressed by question V-16.2.

The two valves in question will be leak tested per the requirements of IWV-3420 with conditions given in Relief Request Basis V20.

d) Questions V-7.8 and V-17 & 18.1.b address compliance with IWV-3426 and IWV-3427, Analysis of Leakage Rates and Corrective Action.

The VYNPC resolution of this issue is included in Relief Request Basis GV-3.

3.

Additional changes included in this program revision are as follows:

a) Pump vibration testing will now be performed in accordance with ANSI /ASNE Draft Standard OH-6, "Inservice testing of Pumps", Draft 11, as noted in Relief Request Basis GP-3.

b) Relief Request Basis GV-2 has been added which changes the acceptance criteria and corrective actions for valve stroke time testing.

The revised criteris and actions are consistent with ANSI /ASME Draft Standard OM-10, "Inservice Testing of Valves", Oraft 11.

4 Reference e), Pump Question 2, addressed testing of the HPCI gland Seal Exhauster and HPCI Hot Well Condensate Pump.

VYNPC response to this item in the October, 1987 meeting with NRC identified these two pieces of equipment as non-safety related and therefore not included in the program.

This equipment has recently been upgraded to Safety Class 3.

Proper operation of this equipment will be demonstrated by acceptable operation of the HPCI system during normal surveil' lance testing.

We continue with our position that these pumus are part of the hDCI SKID and therefore need not be designated specifically in this program.

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