ML20205B939
| ML20205B939 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 03/24/1999 |
| From: | Wang A NRC (Affiliation Not Assigned) |
| To: | Ted Sullivan BOSTON EDISON CO. |
| References | |
| GL-95-07, GL-95-7, TAC-M93504, NUDOCS 9904010032 | |
| Download: ML20205B939 (5) | |
Text
Mr. Theodore A. Sullivan March 24, 1999
. Vice President Nucle:r and Station Director
, Boston Edison Company Pilgriin Nuclear Power Station RFD #1 Rocky Hill Road, Plymouth, MA 02360
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07, " PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," PILGRIM NUCLEAR POWER STATION (TAC NO. M93504)
Dear Mr. Sullivan.
On August 17,1995, the NU issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure those safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their safety functions.
By letter dated February 23,1996, Boston Edison Company (BECo/ licensee) submitted its 180-day response to GL 95-07 for the Pilgrim Nuclear Power Station (PNPS). The NRC staff reviewed the licensee's submittal and requested additional information in a letter dated May 21,1996. By letter dated June 20,1996, the licensee provided additional information.
The NRC staff has reviewed the BECo responses to GL 95-07 for PNPS and has determined that additional information is necessary to complete its safety evaluation. Enclosed is the staff's RAl. We request that you respond by August 15,1999. This response date has been discussed with and agreed upon by Stephen Brennion of your staff.
Questions regarding this request should be sent to my attention at'the above address or you can contact me at (301) 415-1445.-
_ Sincerely, original signed by:
/
' Alan B. Wang, Project Manager Project Directorate 1-2 Division of Licensing Project Management
[
Office of Nuclear Reactor Regulation
__ Docket No. 50-293 s
Enclosure:
Request for Additional Information cc w/ encl: See next page DISTRIBUTION:
1 Docket File EAdensam ACRS PUBLIC TClark CCowgill, RI PDI-2 Reading.
AWang STingen JZwolinski/SBlack OGC
, ;) g g
,rr-
,p
~ "~~" ' ~ " ~ " ' "
DOCUMENT NAME: G: TWANG \\GL9507.WPD To receive a een r of this docunnent, lnd case In t to best "C" = Copy without a ' ichment/ enclosure "E" = Copy with attachment / enclosure "N" = No copy OFFICE PD1-2:PM.
PD1-2:LA A
PD1-2:09 >
NAME AWang W TClark ~$6 EAdens C I
DATE 038199 03/N99 03d09 03/ /99 03/ /99 OFFICIAL RECORD COPY 9904010032 990324 PDR ADOCK 05000293 P
PDR J
ja un, r
g
+4 UNITED STATES P
g j
NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. Samma m*1 k.....,o/
March 24, 1999 Mr. Theodare A. Sullivan Vice President Nuclear and Station Director Boston Edison Company Pilgrim Nuclear Power Station RFD #1 Rocky Hill Road, Plymouth, MA 02360
SUBJECT:
SECOND REQUEST FOR ADDITIONAL INFORMATION - GENERIC LETTER 95-07, " PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES," PILGRIM NUCLEAR POWER STATION (TAC NO. M93504)
Dear Mr. Sullivan:
On August 17,1995, the NRC issued Generic Letter (GL) 95-07, " Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves," to request that licensees take actions to ensure those safety-related power-operated gate valves that are susceptible to pressure locking or thermal binding are capable of performing their ssfety functions.
By letter dated February 23,1996, Boston Edison Company (BECo/ licensee) submitted its 180-day response to GL 95-07 for the Pilgrim Nuclear Power Station (PNPS). The NRC staff reviewed the licensee's submittal and requested additional information in a letter dated May 21,1996. By letter dated June 20,1996, the licensee provided additional information.
The NRC staff has reviewed the BECo responses to GL 95-07 for PNPS and has determined that additional information is necessary to complete its safety evaluation. Enclosed is the staff's RAl. We request that you respond by August 15,1999. This response date has been discussed with and agreed upon by Stephen Brennion of your staff.
Questions regarding this request should be sent to my attention at the above address or you can contact me at (301) 415-1445.
Sincerely, i
Alan B. Wang, oject Manager Project Directorate 1-2 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-293 Encicsure: Request for AdditionalInformation ccw/ encl: See next page
F Mr. Theodore A. Sulliv:n B:tston Edison Comp ny Pilgrim Nucle:r Power Station
~.
cc:
Mr. Ron Ledgett Mr. Jack Alexander Executive Vice President Manager, Reg. Relations and Quality 800 Boyleston Street Assurance Boston, MA 02199 Pilgrim Nuclear Power Station l
RFD #1 Rocky Hill Road Resident inspector Plymouth, MA 02360 U. S. Nuclear Regulatory Commission Pilgrim Nuclear Power Station Mr. David F. Tarantino j
Post Office Box 867 Nuclear information Manager j
l Plymouth, MA 02360 Pilgrim Nuclear Power Station j
l-RFD #1, Rocky Hill Road i
Chairman, Board of Selectmen Plymouth, MA 02360 l
11 Lincoln Street l
Plymouth, MA 02360 Ms. Kathleen M. O'Toole i
Secretary of Public Safety Chairman, Duxbury Board of Selectmen Executive Office of Pubiic Safety Town Hall One Ashburton Place 878 Tremont Street Boston, MA 02108 Duxbury, MA 02332 Mr. Peter LaPorte, Director Office of the Commissioner Attn: James Muckerheide Massachusetts Department of Massachusetts Emergency Management Environmental Protection Agency One Winter Street 400 Worcester Road Boston, MA 02108 P.O. Box 1496 Framingham, MA 01701-0317 l
Office of the Attorney General One Ashburton Place Chairman, Citizens Urging 20th Floor Responsible Energy
)
Boston, MA 02108 P.O. Box 2621 Duxbury, MA 02331 Mr. Robert M. Hallisey, Director Radiation Control Program Citizens at Risk Massachusetts Department of P.O. Box 3803 Public Health Plymouth, MA 02361 305 South Street Boston, MA 02130 W.S. Stowe, Esquire Boston Edison Company Regional Administrator, Region 1 800 Boyleston St.,36th Floor U. S. Nuclear Regulatory Commission Boston, MA 02199 475 Allendale Road King ef Pruesia, PA 19406 Chairman Nuclear Matters Committee Ms. Jane Fleming Town Hall 4
l 8 Oceanwood Drive 11 Lincoln Street Duxbury, MA 0233 Plymouth, MA 02360 Mr. James Keyes Mr. William D. Meinert Acting Licensing Division Manager Nuclear Engineer Boston Edison Company Massachusetts Municipal Wholesale 600 Rocky Hill Road Electric Company Plymouth, MA 02360-5599 P.O. Box 426 Ludlow, MA 01056-0426 o
.r.
.a 1
Ms. Mary Lampert, Director Massachusetts Citizens for Safe Energy 148 Washington Street Duxbury, MA 02332 l
1 l
I i
i l
I l
i
{
9
'i SECOND REQUEST FOR ADDITIONAL INFORMATION PILGRIM NUCLEAR POWER STATION MSf0NSE TO GENERIC LETTER 95-07.
" PRESSURE-LOCKING AND THERMAL-BINDING OF SAFETY-RELATED POWER-OPERATED GATE VALVES" 1.
Is high pressure coolant injection (HPCI) turbine steam admission valve, MO2301-3, required to open following an event that results in a partial depressurization of the reactor coolant system? If so, explain why the valve is not susceptible to pressure locking.
2.
The June 20,1996, Generic Letter 95-07 submittal statos that relief valves were installed in the bonnets of the residual heat removal (RHR) A and B loop torus cooling / spray block valves, MO1001-34A/B, to eliminate the potential for thent.al induced pressure locking. Explain why the valves will not pressure lock when bonnet pressure is less than or equal to the relief valve setpoint but exceeds upstream or downstream pressure.
3.
,The June 20,1996, submittal states that the bonnets of the RHR pump torus suction valves, MO1001-7A/B/C/D, are drained prior to initiating shutdown cooling to eliminate the potential for the valves to pressure lock. Explain if the bonnets could be refilled and repressurized due to seat leakage after being drained. Discuss the potential for any increase in valve temperature if it is possible for the valves to become refilled and repressurized.
4.
Explain why RHR containment spray valves, M01001-23A/B, are not susceptible to pressure locking following surveillance, shutdown cooling and injection evolutions where the bonnets of the valves would be initially pressurized by the RHR pump and j
then required to open later at a lower upstream pressure.
5.
Is the reactor core isolation cooling (RCIC) system declared inoperable when RCIC injection valve, M01301-48, or RCIC turbine steam inlet valves, M01001-16, MO1001-17, are closed? Is the HPCI system declared inoperable when HPCI turbine steam inlet valves, MO2301-4, MO2301-5, are closed? Is the core spray system declared inoperable when core spray injection valves, M01400-24A/B, are closed? If the RCIC, HPCI or core spray systems are considered operable when any of these valves are closed, explain why these valves are not susceptible to pressure locking.
4 ENCLOSURE
- -