ML20203H656
| ML20203H656 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/28/1986 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8608050050 | |
| Download: ML20203H656 (19) | |
Text
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, E 88 aus Docket Nos.: STN 50-454 '
and STN 50-455 LICENSEE: Commonwealth Edison Company FACILITIES: Byron Station, Units 1 and 2
SUBJECT:
MEETING
SUMMARY
- REVIEW 0F BYRON PROGRAM FOR INSERVICE TESTING OF PUMPS AND VAI.VES On July 8 and 9,1986, a meeting was held in Bethesda, Maryland to discuss
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Byron's program for inservice testing of pumps and valves. A list of attendees and questions and answers that were provided during the maeting are enclosed. The licensee committed to submit a' revised program within 60 days of the meeting.
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Enclosures:
As stated Distribution CDocket File, NRC PDR" local PDR .
PD#5 R/F H. Thompson OEl.D V. Noonan L. Olshan E. Jordan J.Partlow B. Grimes ACRS (10)
M. Rushbrook PD#5- D :PDl5 L0ls ahs/ VS nan e6000500soe6072g ADOCK 0500 7//f/86 / PDR P
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- UNITED STATES 8' 4*t NUCLEAR REGULATORY COMMISSION
( $ WASHINGTON, D. C. 20555
%, * *
- p# N 281R$
Docket Nos.: STN 50-454 and STN 50-455 LICENSEE: Commonwealth Edison Company FACILITIES: Byron Station, Units I and 2
SUBJECT:
MEETING
SUMMARY
- REVIEW 0F BYRON PROGRAM FOR INSERVICE TESTING OF PUMPS AND VALVES On July 8 and 9, 1986, a meeting was held in Bethesda, Maryland to discuss Byron's program for inservice testing of pumps and valves. A list of attendees and questions and answers that were provided during the meeting are enclosed. The licensee committed to submit a revised program within 60 days of the meeting.
- r. <
t., N. Olshan, Project Manager PWR Project Directorate #5 Division of PWR l.icensing-A
Enclosures:
As stated I
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Mr. Dennis L. Farrar Byron Station Coninonwealth Edison Company Units I and 2 L
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Mr. William Kortier Ms. Diane Chavez Atomic Power Distribution 528 Gregory Street Westinghouse Electric Corporation Rockford, Illinois 61108 Post Office Box 355 Pittsburgh, Pennsylvania 15230 Regional Administrator, Region III U. S. Nuclear Regulatory Commission Michael Miller 799 Roosevelt Road Isham, Lincoln & Beale Glen Ellyn, Illinois 60137 One First National Plaza 42nd Floor Joseph Gallo, Esq.
Chicago, Illinois 60603 Isham, Lincoln & Beale
, Suite 1100 Mrs. Phillip B. Johnson 1150 Connecticut Avenue, N.W.
1907 Stratford t.ane Washington, D. C. 20036 Rockford, Illinois 61107 Douglass Cassel, Esq.
Dr. Bruce von Zellen 109 N. Dearborn Street
- Department of Biological Sciences Suite 1300 Northern Illinois University Chicago, Illinois 60602 DeKalb, Illinois 61107 Ms. Pat Morrison Mr. Edward R. Crass 5568 Thunderidge Drive Nuclear Safeguards & licensing Rockford, Illinois 61107 Sargent & Lundy Engineers 55 East Monroe Street Ms. Lorraine Creek Chicago, Illinois 60603 Rt. 1, Box 182 Manteno, Illinois 60950 Mr. Julian Hinds U. S. Nuclear Regulatory Comission Byron / Resident Inspectors Offices 4448 German Church Road Byron, Illinois 61010 Mr. Michael C. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety '
1035 Outer Park Drive Springfield, Illinois 62704 l
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, EGzG ldaho NOTEGRAM Cevahelanovassa.
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July 16, 1986 To: Shou-nien Hou From: R. S. HartleytH- ,
Org: NRC/NRR/PWR-A/EB Org. NRR and I&E Support Address: Bethesda, MD Address: EG&G Idaho, Inc.
TRIP REPORT FOR THE PUMP AND VALVE INSERVICE TESTING
, PROGRAM WORKING MEETING FOR THE BYRON STATION, UNIT 1 On July 8 and 9, 1986, a working meeting was held at the NRC offices in Bethesda, Maryland with Commonwealth Edison, NRC, and EG&G Idaho, Inc.
representatives to discuss the questions resulting from the review of the Byron Station, Unit 1, pump and valve inservice testing (IST) program.
Attached is a list of the meeting attendees, the questions that served as an agenda for the meeting, and the responses to those questions as taken from the meeting minutes ana the written responses provided by the licensee. The utility representatives were given a brief introduction outlining the agenda and the methods used for the documentation of questions and responses. This was followed by detailed discussions concerning soecific pumps and valves in the Byron Station program.
These discussions resulted in two open items for the NRC staff and nine open items for the licensee. The open items are also identified in the body of this report.
Attachment:
As Stated cc: E. C. Anderson G. Bagchi, NRR/PWR-A/EB K. Dempsey, NRC/NRR/PAEB S. Hou, NRC/NRR H. L. Magleby C. F. Obenchain L. Olshan, NRR/PWR-A/PD#5 H. C. Rockhold Ti R. S. Hartley File
ATTENDANCE LIST INSERVICE TESTING PROGRAM WORKING MEETING Plant Byron Station. Unit 1 July 8 and 9. 1986 Name Representina Herb Rockhold EG&G Idaho /NRC Scott Hartley EG&G Idaho /NRC Shou-nien Hou NRR/PWR-A/EB J. Philip Toney Commonwealth Edison / Technical Staff Alex Jaworik Commonwealth Edison / Technical Staff Ken Ainger Commonwealth Edison / Technical Staff Kenneth Dempsey NRR/NRC/PAEB G. Bagchi NRR/PWR-A/EB Len Olshan NRR/PWR-A/PD#5 Lynn Conner Doc Search Associates
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BYRON STATION. UNIT 1 PUMP AND VALVE IST PROGRAM COMMENTS AND 00ESTIONS A. General Comments and Questions
- 1. All power operated relief valves in the IST program should be stroke-timed to evaluate possible valve degradation. However, rapid acting valves (i.e., solenoid valves) stroke times may be compared to a reference value for acceptance rather than trending the stroke times per IWV-3413(b) if specific relief is requested.
Response
The staff'* position was discussed and the licensee will modify the rapid acting valve relief request and evaluate 2 seconds as the limiting value and stroke time trending need not be performed. Open item for licensee.
- 2. The NRC staff position is that remote valve position indicators shall be verified during refueling outages not to exceed two years between each verification. Relief request VR-11 is affected by this position.
Response
The utility will revise the relief request to identify individual technical concerns for verification of position indicators. Open item for licensee.
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- 3. The NRC staff position is that valves in the diesel air start systems that perform a function important to safety shall be included in the IST program and tested to the Section XI requirements unless specific relief is requested and sufficient technical justifications are provided to explain why the testing requirements are impractical. Current diesel testing may not verify the operability of each component in the diesel air start system.
Response
The utility will submit a relief request from stroke timing and trending requirements as augmented by the staff for the diesel air start control valves.
- 1. Why were valves lAF-013A-H deleted from the IST program?
Response
The utility shall include either the 1AF-013A-H or the 1AF-005A-H in the IST program and test as category B active valves.
C. Component Coolina Water
- 1. Normally open check valves 1CC9486 performs a safety function in the closed position, therefore, must be considered an " active" valve and demonstration of valve operability must be performed.
Additionally, valves ICC9486, ICC9518, and ICC9534 are check valves that perform a containment isolation function, therefore, should be categorized A/C.
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Response
These valves will be categorized A/C. 1CC9486 will be exercised during cold shutdowns as explained in VR-8.
Valves ICC9518 and 1CC9534 are category A/C passive and need not be exercised.
D. Containment Sprav
- 1. Can check valves ICS003A&B be full-stroke exercised utilizing the pump test line (1SI66AB6) to the RWSTI
Response
The only full flow flowpath through these check valves is through the spray headers in containment consequently spraying equipment with contaminated water resulting in damage to equipment and extensive cleanup operations. The pump test line to the RWST has a flow restriction orifice (1CS01M) which restricts flow to approximately 800 GPM.
Valves ICS003A&B will be partial stroke exercised during quarterly pump tests and full-stroke exercised by dismantling during refueling outages.
- 2. Provide a more specific technical justification for not full-stroke exercising 1CS020A&B quarterly or during cold shutdowns. Why is full-stroke exercising these valves with full flow once every five years possible but not each refueling outage?
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Response
The licensee feels that performing the flow test each refueling outage significantly increases the possibility of introducing the NaOH into the RWST and, therefore, feels the check valve disassembly each refueling outage with the exception of a flow test performed once every five years is the most desirable testing.
- 3. Why were valves ICS010A&B deleted from the IST program?
Response
The staff agrees that these valves are category B passive valves with no testing requirements and therefore need not be included in the IST program. -
, E. Chemical and Volume Control
- 1. Why were valves 1CV8355A,B C&D and ICV 8368A,B,C&D deleted from
- the IST program?
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Response
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l These valves are not currently leak rate tested per Appendix J requirements and are not required to close to perform any safety function and therefore need not be included in the IST program.
l 2. Valve ICV 8113 should be categorized A/C passive.
( Response:
This valve will be categorized A/C.
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- 3. How are check valves ICV 8481A&B full-stroke exercised during !
cold shutdowns? l
Response
Open item for licensee to further evaluate the full-stroke testing capability for these valves and the applicable relief request may be changed.
- 4. Why were the following valves deleted from the IST program?
1CV8480A&8 1CV8110 1CV8111 1CV8346
Response
Valve ICV 8346 is a manually operated, normally closed globe valve and, therefore need not be included in the IST program. Valves ICV 8480A&B, 8110, and 8111 will be included in the IST program as category 8 valves and tested to the code requirements quarterly. Valves 1CV8114 and 8116 will be included in the IST program as category B valves after installation in the system which is expected to be completed at the first refueling outage.
- 5. How is check valve ICV 8546 full-stroke exercised during cold shutdowns?
Response
Open item for licensee to investigate whether the maximum flowrate taken credit for in any accident analyses can be achieved during plant operation through this valve.
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- 6. Provide a more detailed technical justification for not individually exercising and stroke timing valves 1CV8149A,8 and C quarterly during power operation.
Response
Ooen item for licensee and NRC to determine if valves ICV 8149A, 8, and C are required to be in the IST program.
- 7. Is auxiliary spray to the pressurizer via valve 1CV8145 utilized to satisfy the requirements of Reactor Systems Branch technical position RS85-1?
Response
No. ICV 8145 is an air-operated valve, which fails closed on -
a loss of off-site power.
F. Fire protection System
- 1. What is the safety function of valve 1FP0107
Response
This valve is not currently required to be leak rate tested per Appendix J therefore need not be category A.
G. Feedwater System
- 1. Why were valves 1FWO43A through 0 identified as passive when they are full-stroke exercised and stroke timed quarterly?
Response
The word passive in the remarks column will be deleted.
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- 2. Provide the P&ID that shows valves IFWO39A through D.
Response
P&ID was provided.
- 3. Why were valves 1FWO37A through D and 1FWO38A through D deleted from the IST program?
Response
1FWO37A through D internals were removed and are no longer functional. Valves 1FWO38A through D were replaced by IFWO78A through D.
- 4. Do any of the following valves have a reauired fail-safe position?
1FW510A through D 1FW510 1FW520 1FW530 1FW540 1FWO34A through D
Response
For valves 1FWO34A through D the word passive in the remarks
- column will be deleted. Valves 1FW510A through D should be 1FW510A, 520A, 530A, and 540A. These valves do have a required fail-safe position and will be fail safe tested.
The licensee may provide a cold shutdown justification for testing these valves.
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- 5. Do any of the following valves perform a function important to safety in the closed position?
1FWO36A through D 1FWO78A through 0 1FWO79A through D
Response
These check valves perform no safety function in the closed position.
H. Instrument Air
- 1. Passive check valve lIA091 should be categorized "A/C passive" since it is a self actuated (check valve whose leak tight integrity is important for it to perform its safety function.
Response
This valve will be categorized A/C passive.
I. Main Steam System
- 1. Are valves 1MS101A through 0 full-stroke exercised and stroke timed quarterly during power operation?
Response
The word passive in the remarks column will be deleted.
- 2. Are valves 1MS018A through D full-stroke exercised and stroke timed quarterly during power operation? Should these valves be categorized B active?
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Response
These valves will be changed to category B and the word passive in the remarks column will be deleted.
J. Offaas System
- 1. Why were the valves listed in this system identified as
" passive" but still have a stroke and stroke time test performed quarterly?
Response
The word passive in the remarks column will be deleted.
K. Process Radiation Monitorina System
- 1. Provide the P&ID (M-78-6) that shows the valves in this system that were added to the IST program in revision 4.
Response
Valves 1PR002G, IPR 002H, and 1PR032 will be recategorized A/C. P&ID was provided.
L. Process Samplina System
- 1. If the valves in this system are stroke tested quarterly, why are they identified as " passive" in revision 4 to the IST Program?
Response
Valves 1PS9354A&B, IPS9355A&B, 1PS9356A&B, and IPS9357A&B, will have the word passive deleted from the remarks column.
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- 2. Do check valves 1PS231A&B perform any safety function in the open position?
Response
The licensee will investigate to see if indication of flowrate through check valves 1PS231A&B is available to verify full-stroke of these check valves during quarterly testing.
- 3. Rapid acting solenoid operated valves such as 1PS228A&B, IPS229A&B, etc. should be stroke timed to verify they change position in less than some minimum time period (i.e., 2 seconds).
Response
The staff position was discussed and the licensee will modify the rapid acting valve relief request and evaluate 2 seconds as the limiting value and stroke time trending need not be performed. Open item for licensee.
M. Reactor Buildina and Eauipment Drains
- 1. Valves 1RE91598 and 1RE1003 should not be identified as passive if they are periodically opened during plant operation.
Response
The word passive in the remarks column will be deleted.
N. Safety injection System
- 1. Why were the following valves deleted from the IST program?
1SI8919A&B iSI8814 ISI8920 10
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Response
Valves 1SI8919A&B will be included as category C valves and !
tested to the Code requirements. Valves ISI8814 and 1SI8920 l will be included in the IST program as category B valves and tested to the Code requirements.
- 2. Is valve ISI8813 ever required to close during any accident scenario?
Response
1SI8813 is required to close when shifting SI pump suction from the RWST to the containment sump. This valve will be exercised during cold shutdowns since failure in the closed position would render both SI pumps unavailable.
- 3. How are check valves ISI8900A through D and ISI8815 full-stroke exercised during cold shutdowns?
Response
l Open item for licensee to further evaluate if these valves can be full-stroke exercised utilizing the charging pumps I
during cold shutdowns.
- 4. How are check valves ISI8949A&C and 1SI8841A&B full-stroke exercised during cold shutdowns without RHR flow bypassing the reactor core?
Response
l One RHR pump is utilized to provide core cooling the other RHR pump is utilized to full-stroke exercise check valves
, 1SI8949A&C and 1SI8841A&B.
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- 5. How are check valves ISI8948A through D full-stroke exercised during cold shutdowns?
Response
Check valves 1SI8948A through D are partial stroke exercised during cold shutdowns utilizing RHR flow. The licensee has been informed of the staff's position on check valve sample disassembly / inspection for verification of full-stroke capability. Open item for licensee to further evaluate full-stroke exercising these valves.
- 6. What alternate test methods have been considered for demonstration of full-stroke capability for the accumulator outlet check valves ISI8956A through D?
Response
Check valves 1SI8956A through D are burped open during cold shutdowns. The licensee has been informed of the staff's position on check valve sample disassembly / inspection for verification of full-stroke capability. Open item for licensee to further evaluate full-stroke exercising these valves.
O. Essential Service Water System
- 1. Why was the position indicator check (It) deleted for valves 1SX173 and ISX1787
Response
The position indication check for valves 1SX173 and ISX178 was removed as these valves have no remote position indication provided.
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- 2. Does temperature control valve 1SX168 have a reauired fail-safe position?
Response
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Valve is a cubical temperature control valve which serves no
. safety function.
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i 8YRON 1 ADDITIONAL DISCUSSION TOPICS i
Pumos
- 1. Why were the boric acid transfer pumps deleted from the IST program?
Response
Open item for NRC to determine if boric acid transfer pumps need to be included in IST program, i ,2 . Discuss relief request 5--accuracy of ultrasonic flowmeter.
Response
4 Licensee will clarify the discussion of flow instrument accuracies in relief request PR-5.
- 3. Discuss pump vibration alert and required action ranges.
Response
Vibration velocity acceptance criteria acceptable to the staff l
was explained to the licensee.
Valves
- 1. Why was valve ICC9413B deleted from the IST program and RR-87
} Response:
i Valve ICC9413B was deleted from the IST program since it does not perform a containment isolation function and performs no l
other safety related function.
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