ML17139B380
| ML17139B380 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/25/1983 |
| From: | Perch R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8303040359 | |
| Download: ML17139B380 (23) | |
Text
FE'B 24 IQB3 DISTRIBUTION:
See next page
'ocket No.:
50-387/388 APPLICANT:
Penn'syl,vania Power
& Light Company FACILITY:
Susquehanna Steam Electric,'Station, Units 1 and 2
SUBJECT:
SUMMARY
OF JANUARY 25-27, 1983 MEETING CONCERNING IN-,SERVICE INSPECTION PROGRAM (PUMPS
& VALVES)
On January 25-27, 1983, representatives of the Penntsylvania Power
& Light Company ('PP&L) met with members of the NRC staff and their consultants to discuss questions resulting from the review of the Susquehanna, Units 1 and 2, pump and valve in-service test program.
A list of,attendees is provided as Enclosure l.
A brief int'roduction
'outlining the agenda and the methods used for documenting questions and responses was given to PP&L.
This was followed by detailed questions concerning specific pumps and valves in Susquehanna, Units 1 and 2, inservice test program.
The detailed questions and responses are provided as Enclo,sure 2.
~<8~ si~ep Zy.
Or
Enclosures:
As stated R. L. Perch, Project Manager Licensing Branch No. 2 Division of Licensing cc:
See next page PDR ADOCK 05000387 8
I OFFICEI SURNAME/
DATE Q DL:LB82 PM RPerch:pt
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NRG FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981~3&990 /
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Susquehanna Mr. Norman W. Curtis Vice President.
Engineering and Construction Pennsylvania Power 5 Light Company Allentown, Pennsylvania 18101 ccs:
Jay Silberg,. Esquire Shaw, Pittman, Potts 8 Trowbridge 1800 M Street, N.
W.
Washington, D. C. 20036 Edward M. Nagel, Esquire General Counsel and Secretary Pennsylvania Power.
& Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr. William E. Barberich Nuclear Licensing Group Supervisor Pennsylvania Power 5 Light Company 2 North Ninth Street
, Allentown, Pennsylvania 18101 Mr. G. Rhodes Resident Inspector P.'.
Box 52 "Shickshinny, Pennsylvania 18655 Gerald R. Schultz, Esquire Susquehanna Environmental Advocates P. 0. Box 1560 Wilkes-Barre, Pennsylvania 18703 Mr. E. B. Poser Project Engineer Bechtel Power Corporation P. 0. Box 3965.
San Francisco, Califo nia 94119 Ms. Colleen Marsh P. 0. Box 538A, RD $4 Mountain Top, Pennsylvania 18707 Mr. Thomas J. Halligan Correspondent The Citizens Against Nuclear Dangers P. 0. Box 5
- Scranton, Pennsylvania 18501 Mr. J.
W. Millard Project Manager Mail Code 395 General Electric Company 175 Curtner Avenue San Jose, California 95125 Robert W. Adler, Esquire Office of Attorney General 505 Executive House P. 0. Box 2357 Harrisburg, Pennsylvania 17120 Dr. Judith H. Johnsrud Co-Director Environmental Coalition on Nuclear Power 433 Orlando Avenue State College, Pennsylvania 16801 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Resources Commonwealth of Pennsylvania P. 0. Box 2063 Harrisburg, Pennsylvania 17120
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ENCLOSURE 1
LIST OF ATTENDEES NRC PPSL General Ph sics Herb Rockhold (EG&G)
Jerry Cook (EG8G)
Robert Perch*
Thomas Gangloff Edward Wasil.
Frederick Eisenhuth Yince Conciel
- January 27 only
4 E
OSURE 2
A.
General
(}uestions and Comments l.
Are the solenoid valves in the IST program stroke limed?
Response
A relief request will be written for "rapid acting" power operated valves.
These valves with stroke times less than 3-5 seconds will not be trended or stroke times compared to previous tests.
A maximum stroke time will be assigned for each valve where corrective action will be taken if that time is
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exceeded.
Is the frequency of testing of all safety/relief valves in the IST program in accordance with Table IWV-3510-1?
Response
Relief/safety valves are tested at least as frequently as specified in Table IWV-3510-1.
3.
Review the safety related functions of the excess flow check valves to determine if they should be included in the IST program and categorized A/C.
Response
Excess flow check valves will be included in the IST program as category A/C and a relief request provided to permit current Tech.
Spec. testing as a suitable alternative to the Section XI testing (exercising and leak test).
4.
What alternate testing has been considered for meeting the requirements of IWV-3300 for solenoid valves?
Response
Solenoid valves will be individually examined to
, determine what checks are available for verification of indicated valve position.
Individual relief will be requested where necessary.
5.
Relief request number 43 does not apply since all check valves required to open to perform a specific function in shutting down the reactor to the cold shutdown condition or in. mitigating the consequences of an accident must be full stroke exercised or relief requested providing the technical justification for each specific valve that cannot be exercised.
Response
Relief request 43 (Rev.
- 1) will be deleted since the discussion applies to no particular valves.
The general discussion on check valve testing will be incorporated into the IST program for general information.
B.
Emer ency Service Water (M-ill Sheet 2) l.
Oo valves HV-11143 A and B receive any safety related isolation signals?
Response
Valves HV-11143 A and B perform no safety related function and will not be included in the IST program.
2.
Why were valves 1-11-100 and 1-11-101 deleted from the IST program?
Response
The page valves 1-11-100 and 1-11-101 were listed on was inadvertantly left out of the program.
These valves will be included in the next revision of the IST progr am.
Extra Comment Oiesel cooling check valves cannot be positively verified for full-stroke exercising quarterly.
A relief request will be provided for verification of positive valve operability by disassembly at refueling outages (possibly one half of the total number of valves each outage).
2
C..
MSIY Leaka e Control System (M-139) 1.
Were the valves in this system deleted from the IST program or.
was the applicable page omitted from this reviewed copy of the Susquehanna IST program'?
Response
The valves in this system are in the IST program,.
same as Revision 0.
O.
Nuclear Boiler (M-141) 1.
Provide the specific technical justification for not full stroke exercising the AOS valves on a, cold shutdown frequency.
Response
Relief request 810 will be amended, to include a
'discussion why exercising at cold shutdown is impractical (discussion of acustic monitoring, etc.).
2.
Are stop check valves HY-1F032 A and B leak rate tested?
Response
The, "test requirement" column for HV F03ZA will add "L'T" and delete "CV" and HV F032B will add "LT."
These valves will be leak tested once per 2 years per Appendix J.
E.
Control Rod Orive (M-'47) 1.,
How is valve closure (the, safety related position) verified for valves 115 and 138 (185 valves each)?
Response
The relief request will be modified to explain how the test is performed to verify closure of 115 'and 138 valves each refueling outage.
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2.
Provide a more specific technical justification for not full stroke exercising valves XV-1F010 and XV-1F011 quarterly and during cold shutdowns.
Response
Valves XV-1F010 and XV-1F011 will be full-stroke exercised and stroke-timed quarterly.
No relief required.
F.
Reactor Core Isolation Coolin (M-149) 1.,
Should valve 1-49-020 be categorized A passive rather than active?
Response
Valve 1-49-020 will'e categorized A passive.
2.
Why is the phrase "Non-Code Safety Class" utilized in relief request number 20 for valves HV-lF031,, HV-1F059 and HV-1F084?
Response
Valves HV-lF031, 59 and 84 are identified on the ISI boundary drawings as "Non-Code Safety Class,"
however, they do perform a containment isolation function and are exercised per Section XI (except where specific relief is requested).
3.
Should valves FV-lF019, HV-1F060 and HV-1F088 be included in relief request number 20?
Response
FV-lF019, HV-lF060, and HV-1F088 are leak tested in the reverse direction, however, this is permitted by the Code for this type valve.
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I 4
. Provide a more detai.led technical justification for not exercising check valves 1F063 and 1F064 during power operation'or cold shutdowns.
Response
1F063 and 64 require a special test assembly similar to leak rate testing and these tests are normally performed at refueling outages.
5.
Does Susquehanna Steam.Electric Station take credit in any safety analyses for operability of the RCIC pump?
Response
No FSAR credit is taken for the RCIC pump.
G.
Residual Heat Removal (M-151) 1.
Review the safety r elated functions of valve HV-1F021 A and 8 to determine if they should be categorized A.
/
Response
Valves HV-1F021 A and 8 are not currectly included in the list of Appendix J leak rate tested valves and will not be categorized A.
2.
Review the safety related functions of valves HV-1F024 A and 8
and HV-1F027A and 8 to determine if they should be categorized A.
Response
Valves HV-1F024 A and 8 and 27A and 8 are not currently included in the list of Appendix J leak rate tested valves and will not be categorized A,
3.
Oo valves PV-1F051A and 8 perform a pressure isolation function?
Response
Valves PV-1F051 A and 8 do not perform a pressure isolation function and are not leak rate tested.
They will not be categorized A.
4.
Review the safety related functions of valves PSV-1F055A and 8, PSV-15106A and 8; PSV-lF097, and PSV-1F126 to determine if they should be categorized A/C.
Response
PSV-1F055 A and 8, PSV-lF097, and PSV-1F126 will be included in the IST program as Category A/C relief valves.
PSV-15106 A and 8 will be categorized A/C passive and leak rate tested,
- however, they wi 11 not receive the rel'ief valve setpoint test since they are "thermal re 1 iefs."
5.
Provide a more detailed technical justification for not exercising valves 1F090A and 8 quarterly.
Response
Valves 1F090 A and 8 are verified to open quarterly and verified shut during cold shutdown.
Relief request 24 will be expanded to explain why these valves cannot be verified shut quarterly.
6.
Review the safety related functions of the following valves to determine if they should be included in the IST program and categorized as indicated.
Cate or A
HV-1F104 A and 8
(location C-5)
PV-1F052 A and 8
(location 8-8)
~CA/C 1F019
( location G-3)
Response
HV-1F104 A and 8, PV-1F052 A and 8, and 1F019 are not leak rate tested per Appendix J and will not be categorized A or A/C.
These valves are not safety-related and will not be included in IST program.
7.
Provide a more detailed technical justification for not exercising valves HV-1F008 and HV-lF009 during power operation.
Response
HV-1F008 and 9 cannot be exercised during power operation since interlocks exist to prevent opening when'CS pressure is greater than 135 psi.
These valves wi 11 be exercised during cold shutdown.
H.
Core Spray (M-152) 1.
What is the frequency of the "closure test" for check valves 1F030A and 8?
Response
Open item for the utility to determine a method and frequency for verification of closure of valves 1F030 A and 8 (possibly add 29 A and 8 and
'verify closure of "at least, one" in each pair).
Additional Comment Relief request r45 will be expanded to explain why these valves cannot be exercised during power operation.
I.
Hi h Pressure Coolant Injection (M-155) 1.
How is check valve 1F005 full stroke exercised auarterly?
Response
Valve 1F005 is full-stroke exercised quarterly during the pump test from CST to CST.
The relief request wi 11 be deleted.
2.
'i~hat'lternate testing methods have been considered for fdll
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stroke exercising check valve 1F045?
1
Response
OPEN ITEN Utility investigating methods and frequency for full-stroke exercising 1F045.,
3.
Provide a more specific technical justification for not full stroke exercising valves 1F046 and 1F049 quarterly.
Response
Relief request
<32 for valve 1F046 will be deleted.
This valve will be exercised quarterly.
,1F049 will be. exercised open quarterly during HPCI'ump testing.
Valve closure will be verified during the leak rate testing performed during refueling outages.
4.
How is a full stroke exercise of check valve 1F046 verified?
Response
Full-stroke of 1F046 is verified during the HPCI pump
'esting quarterly.
5.
Provide a more specific technical justification for not full stroke exercising valves HV-1F075 and HV-1F079 during power operation.
Response
Valves HV-lF075 and 79 will be full-stroke exercised quarterly.
6.
Review the safety related functions of the following valves to determine if they should be included in the IST program and categorized as indicated.
Cate ory 8 HV-1F011
( 1 ocat ion E-5 )
Category C
IF019
( location D-3)
Response
HV-1F011 will not be included in the IST program.
The utility does not take credit for operability of this valve.
1F019The utility is investigating the safety functions of this valve to determine if valve closure must, be. verified.
J.
HPCI Turbine (M-156) 1.
Why is stroke time not measured for valve FV-15612'?
Response
Maximum stroke time wi 11 be identified in IST program for valve FV-15612.
Additionally, relief request 536 will be deleted.
2.
Why was rupture disc PSE-10003 included in the IST program but not PSE-10004?
Response
- PSE-10004 will be included in the IST program as Category 0.
3.
Review the safety related functions of the HPCI turbine control.
valve, FV-15611, to determine if it should be included in the IST program.
Response
FV-15611 will not be included in the IST program.
This valve is exempted by IWV-1200.
This valve is functionally tested each HPCI pump test but not tested per Section XI.
K.
Containment Atmosphere Control (H-157 Sheet')
l.
Ooes'relief'request 20 apply to all val'ves in this system where "leak test in reverse direction" is utilized in the remarks column?
Response
Relief request 820 only applies to valve HV-15766 in this. system.
All other valves that are leak tested in the reverse direction are allowed this method by IWV-3423.
2.
Oo the Susquehanna Technical Specifications require the valves
'dentified in relief request 37'emain closed during power'peration?
Response
The valves identified in relief request r37 are restricted by Tech.. Specs.
3.6.1.8 to be open
<90 hours per year.
3..
Review the safety related functions of valves PSV-15704A1 thru E2 to determine if they should be included in the IST program.
Response
Valves PSV-15704 Al thru E2 will be included in the IST'program as Category C and are exercised at least quarterly by the pneumatic actuator.
The val'ves are setpoint "tested and back leakage tested every 18 months.,
L.
Control'tructure Chilled Water (N-186) 1.
Provide the specific technical justification for not stroke timing valves HV-08613 A and B quarterly.
Response
Relief request 40 will remain in the program.
The utility will verify if stroke timing of power operated valves can be performed.
M.
Fuel Pool Cool in and Cleanup (M-153) 1..
Review the safety related function of check valves'-53-071 A-and 8 (location F-3) to determine if they should be included in the IST program.
Response
The utilitywill investigate a method and frequency of full-stroke exercising valves 1-53-071 A and B.,
These valves will be included in IST program as Category C.
N.
Service Water (M-109) 1.
Oo valves HV-10943A2 and HV-1094382 perform any safety related functions?
Response
Valves HV-10943A2 and 82 will not be included in the IST'rogram.
They have no safety related function.
P.,
Pump Testin Pro ram 1.,
How are. inlet pressure'and flowrate measured for the standby liquid control pumps during, the pump tests?
Response
The utility will review SLC pump testing procedures
'o determine how parameters are measured during pump testing.
2.
Provide the specific technical justification for not performing quarterly pump testing on the HPCI and standby liquid control l
pumps'esponse:
HPCI and standby liquid control pumps will be tested quarterly.
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k
3.
Provide a more specific technical justification for not performing the quarterly pump test per the ASME code f'r the C. S. chilled water loop circulation pumps and the emergency condenser water circulation pumps.
Response
C.S. chilled water, systems will be functionally tested quarterly as a unit.
4.
How is flowrate measured for the diesel oil transfer pumps?
Response
Diesel oil transfer pump flow will be calculated by measuring level changes in the diesel day tank.
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