L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl

Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl

ML20211K679
Person / Time
Site:	Beaver Valley
Issue date:	08/31/1999
From:	Jain S DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20211K685	List: L-99-022, Forwards Issue 2,Rev 1 to Bvps,Unit 2 Inservice Testing (IST) Program for Pumps & Valves. Summary of Changes,Encl ML20211K687
References
GL-89-04, L-99-022, NUDOCS 9909080049
Download: ML20211K679 (7)

Text

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• Beaver Vaney Power Station Shippingport, PA 15077-0004 SUSHIL C. JAIN . (412) 393-5512 Senior Vice President Fax (724) 643-8069

$$Er* pie $ivision August 31, 1999 L-99-022 U. S. Nuclear Regulatory Commission Document Control Desk

[ Attention:

Washington, DC 20555-0001

)

Subject:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Updated Inservice Testing Program, Issue 2, Revision 1 The purpose of this submittal is to provide the Nuclear Regulatory Commission (NRC) with an informational copy of revisions to the Beaver Valley Power Station Unit 2 (BVPS-2) Inservice Testing (IST) Program.

Enclosure 1 provides a summary of the IST program changes which have been incorporated into Issue 2, Revision 1.

i Enclosure 2 is Issue 2, Revision 1 of the BVPS-2 IST Program. It has been )

determined that the Revision 1 IST program changes do not require NRC approval prior to implementation. This determination was made because all of the changes are either: i i

e in accordance with the ASME/ ANSI Operations and Maintenance Standard i Parts 6 and 10 (OM-6 and OM-10), or e in compliance with the positions delineated in Attachment I and Supplement I of Generic Letter No. 89-04, " Guidance on Developing Acceptable Inservice Testing Programs," or e editorial in nature. (j i* f DELIVERING

~

0UALIiV 9909080049 990031 PDR ADOCK 050004 2 ENERGY

o ,. n- 1; Beaver Valley Pswer Station, Unit No. 2 Updated Inservice Testing Program, Issue 2, Revision 1 Page 2 If you have any questions regarding this submittal, please contact Mr. Mark S.

Ackerman, Manager, Safety & Licensing at (412) 393-5203.

Sincerely, g::: '

Sushil C. Jain I

c: Mr. D. S. Collins, Project Manager

- Mr. D. M. Kern, Sr. Resident Inspector Mr. H. J. Miller, N.RC Region I Administrator l

l 1

ENCLOSURE 1

SUMMARY

OF CHANGES TO THE BVPS-2 IST PROGRAM (ISSUE 2. REV.1. INCLUDING PARTIAL REVS. GA. 0B. OC. OD & OE)

. Added "2 YR - Required every 2 years, but normally done at refueling" to the definitions paragraph in the " Pump Testing Requirements" Section. This was done to accommodate the change below to the Recirculation Spray Pump Outline Sheets. (page 5)

The " type" of Residual Heat Removal Pump [2RHS*P21 A and B) was clarified to be

" Vertical Centrifugal" versus just a vertical pump , (pages 13 and 14) e ' Changed the required frequency of testing for 2BVT 1.13.5 as listed on the " Pump Outline Sheets" for the Recirculation Spray Pumps [2RSS*P21 A-D], from " Refueling (R)" to "2 YR",

although the pumps will continue to be "normally" tested every refueling outage. This was done in accordance with ASME/ ANSI OM-6, Paragraph 5.5, " Pumps Lacking Required Fluid inventory," which states that pumps in dry sumps shall be tested at least once every 2 years. (pages 21-24) e Noted that the Auxiliary Feedwater Pumps [2FEW*P22,23A and 23B] are tested quarteriy "on a staggered test basis" in accordance with Technical Specifications. - (pages 28-30)

' . The Minimum Operating Point (MOP) Curves for the Charging Pumps [2CHS*P21 A, B and C) (pages 55-57) were revised (based on Calculation 10080-N-747-0, A.2) to ensure adequate flow to the reactor coolant system based on installation of new flow orifices in the mini-flow recirculation lines for each pump.

Updated the revision level referenced on the MOP Curve for Calculation 12241-US(B)-193 to "Rev.1 dated 8/24/89", although no changes were made to the minimum operating point (MOP) for the Quench Spray Pumps [2OSS*P21 A and B). (pages 64-65) e Revised the shape of the MOP Curve for the "B" Quench Spray Pump [2OSS*P21B] in accordance with procedure SPEAP 3.1,Section V.P.2., following generation of a new pump curve following maintenance on the pump. (page 65)

. Added a statement to the " Valve Testing Requirements" Section which defines the scope of pressure relief devices in the IST Program. This was an NRC recommendation identified in the SER for the Second 10-Year Interval BVPS-2 IST Program update (Anomaly No.1). (page 84)

• In the " Valve Testing Requirements" Section, Part A, Sections 1 through 4 (page 85),

revised the word " baseline" stroke times to " reference" stroke times to match the wording used in OM-10, Paragraph 4.2.1.8.

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ENCLOSURE 1 (Continued)

SUMMARY

OF CHANGES TO THE BVPS-2 IST PROGRAM (ISSUE 2. REV.1. INCLUDING PARTIAL REVS. 0A. OB. OC. OD & OE)

The " Valve Testing Requirements" Section, Part B on relief valve testing (page 87) was revised to say, "Any safety or relief valve which exceeds its set pressure acceptance criteria (instead of by i3% or greater) shall be repaired or replaced....." This change was made in accordance with the guidance provided in NUREG-1482, Section 4.3.9,

" Clarifications in OM-1, OMc-1994 Addenda to the 1990 Edition of the OM Code", NRC Recommendation (2)a.

Throughout the " Valve Outline" Sheets (pages 94 thru 166), the referenced Operations Surveillance Test (OST) procedure 2OST-47.3A(38) was revised to 2OST-47.3B because the two test procedures were combined into one procedure.

Deleted reference to 2OST-10.6 (previously incorporated into Rev.0A) for leak testing of RHR Pump Suction and Discharge Isolation Valves [2RHS*MOV701 A,701B,702A and 702B] (pages 104 and 105). 2OST-10.6 only performs a qualitative rather than a quantitative leak rate test of these valves while shutting down to refueling. A quantitative leak rate test is subsequently performed by 2OST-10.5 during each refueling outage to meet the requirements of ASME/ ANSI OM-10.

Corrected the referenced surveillance procedure which tests the following valves: [2 SIS *46 and 47), [20SS*3,4 and 267] and [2OSS*MOV102A and B] from 20ST-47.3B to 2OST-1.10. (pages 106,119,120,121,231,252,255 and 256) e Converted VRR1 for SI Accumulator Discharge Check Valves [2 SIS *141,142,145,147, 148 and 151], into VROJ50 based on the NRC recommendation in the SER for the Second 10-Year interval BVPS-2 IST Program update, that relief was not required. (pages 109, 277,278 and 282) e Changed the valve Category from "C" to "A/C" for the following Safety injection Hot and Cold Leg injection Check Valves [2 SIS *545,546,547,548,550 and 552] in order to minimize the possibility of RCS loop recirculation flow by performing leakage monitoring as permitted by ASME/ ANSI Operations & Maintenance Standard, Part 10 (OM-10),

Paragraph 4.2.2.1, " Valve Seat Leakage Rate Test - Scope". (page 110) e Revised the frequency and surveillance test referenced for testing HHSI Discharge to Cold Leg injection Throttle Valves [2 SIS *HCV868A and B] from quarterly in 2OST-47.3B to

" cold shutdown in 2OST-1.10", as justified in new Cold Shutdown Justification "VCSJ10".

These valves have had problems stroking closed with no assistance from flow, however, in order to establish the plant conditions necessary to stroke them with flow, the plant must enter cold shutdown. (pages 112 and 177)

O e Changed the referenced OST for performing remote position verification (RPV) of the Safety injection (Gaseous Nitrogen) valves (page 115), from 2OST-47.3B to 2OST-1.10.

ENCLOSURE 1 (Continued)

SUMMARY

OF CHANGES TO THE BVPS-2 IST PROGRAM -

(ISSUE 2. REV.1. INCLUDING PARTIAL REVS. 0A. 08. OC. OD & OE) i Deleted Valve' Cold Shutdown Justifications VCSJ's 10 and 11 for Containment Aribome

. Activity Radiation Monitor inlet and Outlet isolation Valves [2CVS*SOV102,153A and i 153B] (pages 116 and 117) because the valves are capable of safely being tested while at power. Moved cold shutdown testing of these valves from 2OST-1.10 to 2OST-47.38 (quarterly).

On the " Valve Outine" Sheets for Turbine Driven AFW Pump Steam Supply Valves 1

[2 MSS *SOV105A thru F] (pages 137 and 138), added reference to 2OST-47.3B which is performed during Modes 4,5 and 6 (when no steam supply is available) to stroke and time these valves in the open and closed directions as required quarterly by Yechnical Specifications. 20ST-24.4 will continue to stroke and time the valves quarterly when steam is available in Modes 1-3.

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. Revision OE changed the forward full-stroke test method for Steam Generator Residual Heat Release Check Valves [2SVS*80,81 and 82] (page 140) to a disessembly and inspection. Revision 1 has provided reference to the maintenance procedure (1/2 CMP ENERTECH CHECK-1M) which will perform the " sample" inspections. It was also O determined that to disassemble and inspect all three check valves during each refueling outage was considered burdensome. Therefore, a sample disassembly and inspection plan was developed as permitted by and in accordance with Generic Letter No. 89-04, Position 2. Valve Refueling Outage Justification No. 51 (VROJ51) was also revised accordingly (pages 279 and 280). In addition, the full-stroke exercise referenced in the "Altemate Test" section of VROJ No.41 (page 265) was revised from VCSJ No.18 to "VROJ No.51".

. Corrected the valve " Class" for the Main Feedwater Regulating Valves [ 2FWS*FCV478, 488 and 498] from 2 to 3. (page 141) e Revised the " Station Log 3" referenced for leakage monitoring of AFW Pump Discharge to S/G Check Valves [2FWE*42A,42B,43A,438,44A and 448) (page 142) from L3 to q "PAB2". l

. Changed the referenced OST for performing remote position verification (RPV) of the Primary Plant Domineralized Water Storage Tank Suction isolation Valves i

[2FWE*SOV100A and B] (page 143), from 2OST-47.3B to 2OST-1.10. Also corrected the  ;

NSA position from shut (S) to open (O). l

. Added the words "By Leak Test" to the full stroke (FS), reverse direction (RD) " Comments" on the " Valve Outline" sheet (page 149) for Service Water Header Check Valves O [2SWS*106 and 107]. Also added additional justification to Valve Refueling Outage Justification No. 45 (page 271) dealing with the leakage testing performed to verify check valve closure, and more detail about the test method (s) employed.

ENCLOSURE 1 (Continued)

SUMMARY

OF CHANGES TO THE BVPS-2 IST PROGRAM llSSUE 2. REV.1. INCLUDING PARTIAL REVS. 0A. 08. OC. OD & OE) e Deleted the " passive" Service Water Supply Valves [2SWS*MOV1138 and C] to the Emergency Diesel Generator heat exchangers from the BVPS-2 IST Program because they are not required to change positions during an accident and are no longer stroked per Generic Letter No. 96-05 concems. (page150) e Corrected the referenced surveillance procedure which tests Service Water Pump Vacuum Break Check Valves [2SWS*486 and 487] in the forward direction, to only 2OST-30.6. j (pages 151 and 152) e Clarified in the " Basis for CSJ" in VCSJ32 that fail-safe testing must be performed following a " loss of valve actuating power" as it is stated in ASME/ ANSI OM-10, Paragraph 4.2.1.6,

" Fall-Safe Valve". (page 202) e Corrected the reference to OM-10, Paragraph 4.2.1.2(c) in the " Basis for ROJ" for the following valvesNROJ's. Each VROJ had erroneously referenced Paragraph 4.3.2.2(c) which is for check valves.

. VROJ28

[2 SIS *MOV836] (page 245) e [2 SIS *MOV869A,B] VROJ29 (page 247) e VROJ30

[2 SIS *MOV8889] (pagd 249) e [2SWS*MOV103A,B] VROJ46 (page 272) e Clarified in the " Alternate Test" in VRR2 that the limiting stroke time of $10 seconds is based on the EDG starting requirements only and not on ESF response time. (page 283)

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ENCLOSURE 2 BVPS-2 IST Program (Issue 2, Revision 1)

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