ML17164B016
| ML17164B016 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/22/1999 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| GL-97-07, GL-97-7, TAC-M93528, TAC-M93529, NUDOCS 9904280058 | |
| Download: ML17164B016 (6) | |
Text
Apri1 22, 1999 MEMORANDUMTO: Docket File Origina1 signed by.-
FROM:
Victor Nerses, Senior, Project'Manager, Section 1
Project Directorate I,'ivision of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2,
'RAFT REQUEST FOR ADDITIONALINFORMATION,GL 97-07:
PRESSURE LOCKINGAND THERMALBINDINGOF SAFETY RELATED POWER, OPERATED GATE VALVES(TAC NOS. M93528 AND M93529)
The attached request for additional information (RAI) was transmitted by facsmile on 1
April 22, 1999, to N. Coddington of PPS I, Inc. Review of the RAI vyould allow the licensee to determine and agree upon a'schedule to respond to the RAI. This memorandum and the attached do not convey a formal request for information or represent an NRC staff position.
Docket Nos. 50-387 and 50-388
Attachment:
As stated DISTRIBUTION:
cDocke~tFile PUBLIC S. Bajwa V. Nerses OFFICE NAME DATE PDI-1/PM J. 4i e ses:Icc Vi +99 OFFICIALRECORD COPY DOCUMENT NAME: G:)SUSQNEM93528.WPD n "tQ0~~
990428005S 990422 PDR ADOCK 0500038'7 P
PDR N4>>> @+
April 22, 1999 MEMORANDUMTO: Docket File FROM:
Victor Ners Original signed by:
es, Senior Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONALINFORMATION,GL 97-07:
PRESSURE LOCKINGAND THERMALBINDINGOF SAFETY RELATED POWER OPERATED GATE VALVES(TAC NOS. M93528 AND M93529)
The attached request for additional information (RAI) was transmitted by facsmile on April 22, 1999, to N. Coddington of PP&L, Inc. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attached do not convey a formal request for information or represent an NRC staff position.
Docket Nos. 50-387 and 50-388
Attachment:
As stated DISTRIBUTION:
Docket File PUBLIC S. Bajwa V. Nerses OFFICE NAME DATE PDI-1/PM ses:Icc I// Q99 FFIC 0
IALRECORD COPY DOCUMENT NAME: G:FSUSQNEM93528.WPD
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 20555-000I April 22, 1999 MEMORANDUMTO: DockgPlh evictor Nerses, Senior jsroject Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2, DRAFT REQUEST FOR ADDITIONALINFORMATION,GL 97-07:
PRESSURE LOCKINGAND THERMALBINDINGOF SAFETY RELATED POWER OPERATED GATE VALVES (TAC NOS: M93528 AND M93529)
The attached request for additional information (RAI) was transmitted by facsmile on April 22, 1999, to N. Coddington of PP8 L, Inc. Review of the RAI would allow the licensee to determine and agree upon a schedule to respond to the RAI. This memorandum and the attached do not convey a formal request for information or represent an NRC staff position.
Docket Nos. 50-387 and 50-388
Attachment:
As stated
DRAFT RAI ON GL 95-07: PRESSURE LOCKINGAND THERMALBINDINGOF SAFETY RELATED POWER OPERATED GATE VALVES
- 1. Your submittal dated July 1, 1998, states that the residual heat removal (RHR) heat exchanger outlet valves, HV-1(2)51-F003NB, are susceptible to thermal binding and precautions were added to the procedures as corrective action. Describe the procedures revisions that were implemented to prevent the valves from thermal binding.
- 2. Your submittal dated November 7, 1998, states that the high pressure coolant injection (HPCI) turbine steam admission valve, HV-1(2)55-F001, is not susceptible to pressure locking because the bonnet is filled with steam.
Explain why a valve with only steam in the bonnet is not susceptible to pressure locking. Explain if these valves are susceptible to pressure locking during an event that results in a reduction in reactor pressure but reactor pressure remains high enough to operate the HPCI turbine. During this type of event, pressure in the bonnets of the valves could be higher than upstream and downstream pressure when the valves are required to open.
Describe any other valves that were not considered susceptible to pressure locking because there is only steam in their bonnets.
- 3. The NRC request for information dated June 10, 1996, asked if the reactor core isolation cooling (RCIC) pump suppression pool suction valves, HV-1(2)49-F031, were included in the scope of GL 95-07. Your response dated July 11, 1996, stated that the valves are not included in the scope of GL 95-07 because the RCIC system is not considered safety related.
Verifythat the RCIC system is not required for the mitigation of any licensing basis events.
Your, IST Program states that these valves have an open safety position. Your submittal states that these valves are included in the GL 89-10 Program.
Supplement 6 to GL 89-10 required that licensee's evaluate motor-operated valves for pressure locking and thermal binding. Explain how these valves can be included in the GL 89-10 Program without evaluating them for pressure locking and thermal binding and why your IST Program states that the valves have an open function.
- 4. Your submittal dated July 1, 1998, states that the RHR Heat Exchanger inlet valves, HV-1(2)51-F047NB, are susceptible to pressure locking if the RHR pump trips when the valve is closed during the shutdown cooling mode of operation.
As corrective action, procedures were revised to provide operator guidance to take the appropriate actions.
Describe the appropriate actions.
Attachment
P A