ML18030A268
| ML18030A268 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/28/1981 |
| From: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| PLA-748, NUDOCS 8105050442 | |
| Download: ML18030A268 (4) | |
Text
REGULATO INFORMATIO~ DISTRIBUTION STEM (RIOS)
ACCESSION NBR: 8105050442 DOC ~ DATE: 81/04/28 NOTARIZED!
NO FACII.:50-387 Susquehanna Steam Electric Stationt Unit 1 t Pennsyl va 50 388 Susquehanna Steam Electric Stationt Unit 2t Pennsylva AUTH'AME AUTHOR AFFILIATION CURTEStV ~
'tre Pennsylvania Power 8 Light Coo REC IP, NAME
.RECIPIENT AFFILIATION YOUNGBLOOOtS,J.
l.icensing Sr anch 1
SUBJECT:
Submits info in respanse to NRC concerns on leaktight integrity of primar y coalant sys pr assure isolation valves.
Leak testing will be performed every 18 months 8 limiting conditions for operation incorpor'ated into Tech Specs.
DISTRIBUTION CODE:
8001S COl'IES RECEIVED:LTR ~ENCL SIZE:
TITLE: PSAR/FSAR AMOTS and Related Correspondence NOTES:Send I8E 3 copies FSAR 8 all amends'end I8E 3 copies FSAR 8 all
- amends, DOCKET ¹ 0500038 05000388 05000387 05000388 RECIPIFNT 10 CODE/RAMP ACTION:
A/0 LICENSNG RUSHBROOKtM, INTERNAL: ACCID EV AL BR26 CHEM E.VG BR 08 CORE PERF BR 10 EMERG PREP 22 GEOSCIENCES 14 HYO/GEO GR 1b I8E Ot LIC QUAL BR MECH ENG SR ie NRC POR 02 OP LIC BR PROC/TST REV 20 SEMESS BR22 EG ILE 01 S
ENG 8R25 COPIES LTTR ENCL 1
1 1
1 1
1 3
1 1
1 1
1 1
1 1
RECIPIENT IO CODE/NAME LIC BR ¹2 BC STARKtR ~
04 AUX SYS SR 07 CONT SYS BR 09 EFF TR SYS BR12 EQUIP QUAL BR13
'HUM FACT ENG BR I8C SYS BR 16 L IC GUIO BR MATL ENG BR 17 MPA OELO PONER SYS RR 19 QA SR 21 REAC SYS BR 23 SIT ANAL BR 24 COP IES LTTR ENC 1
1 EXTERNAL: ACRS NSIC 27 05 LPDR 03 MN 06 1981 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 56 ENCL
TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONE: t215) 170-5151 NORMAN W. CURTIS Vice President-Engineering 8 Construction-Nuclear 770 5381April 28, 1981 Docket Nos.
50-387 50-388 Mr. B. J. Youngblood, Chief-Licensing Branch No.
1 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 SUSQUEHANNA STEAM ELECTRIC STATION LEAKTZGHT INTEGRITY OF PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES ER 100450 FILE 841-2 PLA-748
Dear Mr. Youngblood:
The following is in response to a concern which was expressed at a meeting between PPGL and the NRC-Mechanical Engineering Branch.
NRC Position l.
A minimum of 2 valve isolations are required between RCS and low pressure systems.
The Class 1 to Class 2 boundary is considered the isolation point.
2.
A water leak test will be performed on 2 of the pressure isolation valves at each interface utilizing system operating 5p with an acceptance criterion of 1 gpm per valve.
3.
Leak test frequency will be once per refueling outage, prior to return to service following valve maintenance, and following each time the valve is cycled.
4.
Technical Specifications will provide LCO/Surveillance for those pressure isolation valves which will also be categorized as A or AC in the pump and valve ZSZ program.
PL Position 1.
The following high/low pressure interfaces are within the scope of the NRC requirements:
1ST ISOLATION VALVE(S)
NUMBER(S)
HV-1F006A HV-1F037A TYPE Check Globe 2ND ISOLATION VALVE(S) NUMBER(S)
TYPE SERVICE HV-1F005A Gate Core Spray Injection HV-1F006B HV-1F037B Check Globe HV-1F005B Gate Core Spray Injection PENNSYLVANIA POWER 8
LIGHT COMPANY
Mr. B. J.
Youngblood April 28, 1981 HV-1FOSOA HV-1F122A HV-1F050B HV-1F122B Check Globe Check Globe HV-1F015A HV-1F015B Gate LPCZ Injection Gate LPCZ Injection HV-1F-22 Gate HV-1F033 Globe Head Spray HV-1F009 Gate HV-lF008 Gate Shutdown Cooling 2.
Leak testing will be provided for pressure isolation valves at a frequency of once per 18 months, and prior to returning to service following valve maintenance that could affect valve leak tightness.
This will be a water test with acceptance criteria of 1 gpm for a test
~ equal to reactor operating pressure.
An alternative to this water test is adoption of a leakage limit for each valve undergoing Type C
testing (10 CFR 50, Appendix J) which provides assurance that the 1 gpm water leakage criteria is met.
3.
Fre enc of Testin Leakage testing will be performed at a convenient point once per 18 months and following maintenance which could affect valve leak tightness.
No commitment is made to testing immediately prior to entering OPERATIONAL CONDITION 2 on startup or to testing following valve actuation; alternative means of assuring valve position are utilized.
Where available, direct indication of valve position will assure that the pressure isolation function is being provided.
For valves where no direct position indication exists, plant startups will be initiated with the other pressure isolation valves open.
Plant pressurization will connect and the other valves (with direct position indication) will not be closed until pressure isolation of the first valve is verified by pressure instrumentation readings.
4.
Pressure Isolation Valve Limiting Conditions for Operation and Surveillance testing requirements will be incorporated into the Technical Specifications.
These valves will be categorized A or AC as appropriate in the Pump and Valve ISZ Program.
Very truly yours, N.
W. Curtis Vice President-Engineering and Construction-Nuclear RRS:mcb