BECO-88-136, Responds to NRC Bulletin 85-003,Suppl 1 Requesting Reexam & Possible Expansion of Licensee Valve Testing Programs to Verify Torgue Switch Settings on safety-related motor-operated Valves

Responds to NRC Bulletin 85-003,Suppl 1 Requesting Reexam & Possible Expansion of Licensee Valve Testing Programs to Verify Torgue Switch Settings on safety-related motor-operated Valves

ML20154J690
Person / Time
Site:	Pilgrim
Issue date:	09/17/1988
From:	Bird R BOSTON EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
BECO-88-136, IEB-85-003, IEB-85-3, NUDOCS 8809230110
Download: ML20154J690 (5)

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NRC Bulletin 85-03  !

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eosnwanson Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 September 17, 1988 Ralph G. Bird BECo 88 136 Senior Vice President - Nuclear U. S. Nuclear Regulatory Commission Document Control Desk Hashington, DC 20555 1.icense DPR-35 Docket 50-293 BESPONSE TO ERC BULLETIN 85-03. SUPPLEMENT I This letter provides our response to NRC Bulletin 85-03, Supplement 1, which requested a re-examination and possible expansion of licensees' valve testing programs to verify the torque switch settings on safety related motor operated valves (H0Vs). Since the issuance of this Bulletin supplement, the NRC by

, letter of August 8,1988 has accepted the revised Boiling Hater Reactor Owners Grcup (BHROG) report, NEDC 31322 Supplement 1, dated July 20, 1988.

He endorse the methodology of NEDC-31322 Supplement 1 for the selection of valves and their maximum expected diffe'ential pressure. Our endorsement results in no valves being added to the 21 H0V's reported to the NRC in our original Bulletin 85-03 response of December 31, 1986. It does result in a data change for two of the original 21 valves, which is reported in this letter's attaG1 ment. The attachment also lists two new valves which we*e added to Pilgrim as a result of plant modifications made during this outage.

Boston Edison will complete Bulletin 85-03 activities in accordance with the schedule approved by the NRC letter dated April 14, 1988.

Attachri.ent PMK/amm/2454 cc: M.. D. Mcdonald, Project Manager Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D. C. 20555 U. S. Nuclear Regulatary Conmission Region I 475 Allendale Road King of Prussia, PA 19406 Senior NRC Resident inspector Pilgrim Nuclear Power Station 8009230110 000917 PDR ADOCK 0000 3 ,g

r Attachment to NRC Bulletin 85-03. Sucolement 1 Boston Edison provided data on 21 HOVs affected by Bulletin 85-03 in our letter of December 31, 1986. He have re-tvaluatad that data based on Supplement 1 and provided a data update on the following two pages. Changes are designated by a change bar in the right hand margin.

Changes to the original list are:

1) MO-2301-6 Maximum Openingz1 P rose from 25 psi to 40 psi.

2) H0-1301 -22 Maximum Opening /l P rose from 25 psi to 38 psi.

Two new valves were added to the list to reflect their addition to Pilgrim.

The new valves are shown on the attached schematic drawing of the HPCI Steam Lines Motor Operated Valves.

They are:

1) H0-2301-33 Vacuum Breaker Line Isolation Valve

2) H0-2301-34 Vacuum Breaker Line Isolation Valve

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tiOV DATA SUMMADJ ,'-

Tcrquy Size (in) Limitorque DesignIBasis Max Operating 2 Switch '

HPCI Systes Valve Ratina(Ib) Oserator Valvo Function AP (PSI) A P(PSI) Open/Close Jussered -

M0-2301-3 10x8 SMB-1 Steam Admission Valve 1150 1104/1104 Open Valan - Gate 600 MO-2301-4 10x8 SMB-2 Steam Lin.e Isolation Valve 1150 1104/1104 Open Velan - Gate 900 MO-2301-5 10x8 SMB-1 Steam Line Isolation Valve 1150 1104/1104 Open Velan - Gate 600 MD-2'01-6 16 SMB-0 Condensate Storage Tank 60 40/38 Open Powell - Gate 150 Suction Valve MD-2301-8 14x10 SMB-1 Injection Valve 1500 1230/1302 Open Anchor - Gate 900 MO-2301-9 14x10 SM8-1 Injection Test Valve 1E'O 1230/1302 Open Anchor - Gate 900 MO-2501-10 10 SMB-2 CST Test Return Valve 1500 1290/1337 Open Velan - Gir,oe 900 M0-2301-14 4 SMB-0 Minimus Flow Bypass 1500 1327/1355 Open Valan - Globe 900 Isolation Valve MO-2301-33 4 SMB-000 Vacuum Breaker Liae 135 45/45 Open Powell-Gate 150 Isolation Valve MO-2301-34 4 SMB-000 Vacuum Breaker Line 135 45/45 Open -

Powell-Gate 150 Ise!ation Valve MO-2301-35 16 SMB-0 Suppression Pool Suction 60 263/26 Open Powell - Gate 150 Isolation Valve M0-2301-36 16 SMB-00 Suppression Pool Suction 60 273/27 Open Anchor - Gate 150 Isolation Valve 1 Values are for both open and close positions.

2 Calculated maxirwm operating pressures based on BW" ner's Group Report. '

3 For additional conservatism, increasing pressure due. to check valve leakage will be assumed resulting in a suction line pressure of 97 psi. Realizing this possibility, the suction line relief valve will be set lower, er the val-?s/ operators will be readjusted for 100 psi differential.

m MOV GATA StEMARY (Cont'd) .

Torque ','

Size (in) Limitorque DesignlBasis Max Operating 2 Switch -

RCIC System Valve Ratina(Ib) Operator Yalve Function A P (PSI) A P(PSI) Ooen/Close _Jumpertd_ _

M0-1301-16 3 SMB-00 Steam Line Isolation Valve 1250 1104/1104 Open Westinghouse - Gate 600 MO-1301-17 3 SMB-000 Steam Line Isolation Vaive 1250  : 04/11')4 Open Velan - Gate 600 MG-1301-22 6 SMB-000 Condensate Storage Tank 60 38/36 Open Pcwell - Gata 150 Suction Valve M0-1301-25 6 SMB-000 Suppression Pool Suction 60 273/27 Open Valan - Gate 150 Isolation Valve M0-1301-26 6 SMB-000 Suppression Pool Suction 60 263/26 Open Powell - Gate 150 Isolation Valve MD-1301-48 4 SMB-00 Injection Tect Vaive 1500 1238/1345 Open Powell - Gate 900 M0-1301-49 4 SMB-00 Injection Valve 1400 1238/1345 Open Powell - Gate 900 MD-1301-53 4 SMB-0 CST Test Return Valve 1400 1301/1358 Open Pow 211 - Globe 900 H0-1301-60 2 SMB-00 Minimum Flow Bypass 1500 1340/1377 Open Powell - Globe 600 Isolation Valve M0-1301-61 3 SMB-00 Steam Admission Valve 1150 1104/1104 Open Powell - Globe 600 M0-1301-62 2 SMB-000 Cooling Water to Turbine 75 604/28 Open Powell - Globe 600 Accessories )

I Values are for both open and close positlocs.

2 Calculated maximum operating pressures based on BHR Owner's Group Report.

3 Fcr 7 5.tlonal conservatism, increasing pressure due to check valve leakage will be assumed resulting in a suction line pressure of 95 psi. Realizing this possibility, the suction line relief valve will be set lower or the valves / operators will be readjusted for 100 psi differential.

4 This value is based on demonstrated operability during pump survelliance testing, and a control valve located upstream.

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