ML20235V727

Notification of Forthcoming Meeting W/Util in Southport,Nc to Discuss Pump & Valve Inservice Testing Program.Agenda Will Follow Encl Questions & Comments

ML20235V727
Person / Time
Site:	Brunswick
Issue date:	07/15/1987
From:	Sylvester E Office of Nuclear Reactor Regulation
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8707230286
Download: ML20235V727 (13)

Text

_ _ _ _ _ _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ -_

t 4

Docket NO. 50-325/324 DISTRIBUTION:

See attached list MEMORANDUM FOR: Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II FROM: Ernest Sylvester, Project Manager Project Directorate 11-1 Division of Reactor Projects I/II

SUBJECT:

FORTHCOMING MEETING WITH CAROLINA POWER & LIGHT CO.

BRUNSWICK STEAM ELECTRIC PLANT (BSEP), UNITS 1 AND 2 LOCATION: Brunswick Steam Electric Plant, Southport, NC PURPOSE: To discuss the BSEP pump and valve inservice testing program.

The agenda will follow the enclosed " Questions and Comments."

PARTICIPANTS: NRC NRC CONSULTANTS CP&L E. Adensam T. Cook B. Blinson H. Shaw S. Hartley J. Brobson E. Sylvester P. Godsey B. Teletzke L. VanEden L. Wheatley Ernest Sylvester, Project Manager Project Directorate 11-1 Division of Reactor Projects I/II

Enclosure:

As stated cc: See next page

• Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, interveners, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"

43 Federal Register 28058, 6/28/78.

PD:PD21:DRPR ESlyvester/dsf 7/6s'/87 8707230286 870715 PDR P

ADOCK 05000324 PDR k

)

I

i JUL 15 G37 Docket NO. 50-325/324 DISTRIBUTION:

See attached list MEMORANDUM FOR: Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects 1/11 i FROM: Ernest Sylvester, Project Manager Project Directorate 11-1 Division of Reactor Projects I/11 q

SUBJECT:

FORTHCOMING MEETING WITH CAROLINA POWER & LIGHT CO.

BRUNSWICK STEAM ELECTRIC PLANT (BSEP), UNITS 1 AND 2 LOCATION: Brunswick Ste c Flectric Plant, Southport, NC PURPOSE: To discuss the BSEP pump and valve inservice testing program.

The agenda will follow the enclosed " Questions and Comments."

PARTICIPANTS: NRC NRC CONSULTANTS CP&L E. Adensam T. Cook B. Blinson H. Shaw S. Hartley J. Brobson E. Sylvester P. Godsey B. Teletzke L. VanEden L. Wheatley Ernest Sylvester, Project Manager Project Directorate 11-1 Division of Reactor Projects 1/11

Enclosure:

As stated cc: See next pace I

• Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, interveners, or other parties to attend as observers pursuant to "Open Meeting Statement of NRC Staff Policy,"

43 Federal Register 28058,6/28/78.

PD:PD21:DRPR ESlyvester/dsf 7/ts"/87 I

Y

Mr. E. E. Utley Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:

Mr. P. W. Howe Mr. C. R. Dietz Vice President Plant General Manager Brunswick Nuclear Project Brunswick Nuclear Project 1 Box 10429 Box 10429 l Southport, North Carolina 28461 Southport, North Carolina 28461 l Thomas A. Baxter, Esquire Mr. H. A. Cole Shaw, Pittman, Potts & Trowbridge Special Deputy Attorney General 2300 N Street, N. W. State of North Carolina Washington, D. C. 20037 Post Office Box 629 i

Raleigh, North Carolina 27602 Mr. D. E. Hollar Associate General Counsel Mr. Robert P. Gruber I

' Carolina Power & Light Company Executive Director Post Office Box 1551 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 -

Mr. Christopher Chappell, Chairman Board of Commissioners Post Office Box 249 Bolivia, North Carolina 28422 Mrs. Chrys Baggett ,

State Clearinghouse Budget and Management 116 West Jones Street Raleigh, North Carolina 27603 Resident Inspector U. S. Nuclear Regulatory Commission Star Route 1 Post Office Box 208 Southport, North Carolina 28461  ;

Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Dayne H. Brown, Chief l Radiation Protection Branch Division of Facility Services N. C. Department of Human Resources 701 Barbour Drive Raleigh, North Carolina 27603-2008

{

l 's

' BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AND 2 1

l- PUMP AND VALVE INSERVICE TESTING PROGRAM i

QUESTIONS AND COMMENTS

1. VALVE TESTING PROGRAM A. General Questions and comments

1. Are all valves that are Appendix J, type'C, leak tested included in the IST program and categorized A or A/C7

- 2. Provide a listing of the limiting values of. full-stroke time for all power operated valves in the Brunswick IST program for our review.

3. Does the control room ventilation system perform any ,

I safety-related function? If so, the appropriate support system valves should be included in the IST program.

B. Service Water System i

1. Has the service water lubricating water system deactivation been

]

completed or is it still scheduled to be completed in late 1987 (See valve relief request VR-15)? Does this relief request also  ;

apply to Unit 27 C. Diesel Generator Service Water System

1. How are valves SW-272, 273, 274, and 275 verified shut quarterly?

D. Containment Atmospheric Control System i

1. Are valves CAC-X18A through J equipped with position indication?

If not, how is the closed position verified during quarterly exercising?

1

2. Does valve relief request VR-03 apply to valves 1-CAC-V160 and 162?

3. What is the P&ID location of valves 2-CAC-PV4344 and -PV4345?

Should these valves be identified as SV-4344 and SV-4345?

4. Valve 2-CAC-V170 is listed in the Valve Tables on the wrong P&IO.

1 i Is this valve equipped with a solenoid operator instead of an air operator?

5. Is valve 2-CAC-V171 equipped with a solenoid operator instead of an air operator?

E. Control Rod Drive Hydraulic System

1. How are valves C11-115 and 138 verified to close during control rod scram testing? l

2. How are valves C11-126 and 127 stroke timed during exercising? J F. Reactor Coolant Recirculation System

1. Provide a more detailed technical justification for not full-stroke exercising all excess flow check valves quarterly and during cold shutdown.

2. What is the normal position of valves B32-F032A and 032B7 (See valve cold shutdown justification VC-01)

G. Nuclear Steam Supply System  !

1. What is the exercising frequency for the ADS valves? The IST

. program Valve Tables, p-19, do not agree with valve relief request VR-07.

2

t

2. Provide a more detailed technical justification for not full-stroke exercising valves B21-F037A through H, J, K, and L during cold shutdowns.

H. High pressure Coolant Injection System

1. Provide a detailed technical justification for not full-stroke exercising valve 1-E41-F002 quarterly.

2. Does valve E41-F019 perform a safety-related function in the l closed position?

l

3. How is valve E41-F046 verified to full-stroke open quarterly?

4. How are valves E41-V93 and 94 individually verified to close quarterly?

5. Review the safety-related function of valve E41-F011 (P& ids D-25023 and D-2523,SH-1, coordinates F-3) to determine if it should be included in the IST program-and tested to the Code requirements.

6. Previde a detailed technical justification for not full-stroke exercising valves E41-F021 and 022 quarterly.

7. How is valve E41-F045 verified to full-stroke quarterly? .

8. How is stroke time measured while exercising valves E41-V8 and V9 l

quarterly?

9. Review the safety-related function of the following valves to determine if they should be included in the IST program and tested to the Code requirements: l l

3

t '

l Valve P&lD & coordinates E41-F026 D-25023 SH-2 (A-4) .

D-2523 SH-2 (A-4) l E41-F028 D-25023 SH-2 (E-2)

D-2523 SH-2 (E-2) 1 E41-F076 D-25023 SH-2 (B-8)

D-2523 SH-2 (B-8) l E41-F077 D-25023 SH-2 (B-8) i D-2523 SH-2 (B-8) I l

I. Core Spray System I l

1. What are the consequences of injecting condensate water into the reactor vessel during cold shutdown? (see valve relief request i VR-09) l l

2. Is valve E21-F0078 locked open as indicated on P&ID D-25024 SH-17

3. How are valves E21-F029B and 30B individually verified to close quarterly?

i J. Residual Heat Removal System

1. Provide a more detailed technical justification for not full-stroke exercising valves E11-F004A, B, C, and D and E11-F006A, B, C, and D quarterly. Why is the exercising frequency for the Unit i valves different than that for the Unit 2 valves?

2. Why is the exercising direction of valve 1-E11-F016A different than that of valve 2-E11-F016A?

3. Valves 2-E11-F031B and -F031D are listed twice in the Valve Tables.

4

R s

4. How are valves E11-F046A, B, C, and D verified to full-stroke exercise quarterly?

5. How are valves E11-V192 and 193 and valves E11-F089 and 090 individually verified to close quarterly? j l

6. Provide a detailed technical justification for not exercising  ;

valves E11-F022 and 023 quarterly in accordance with the Code requirements.

7. Review the safety-related function of the following valves to determine if they should be included in the IST program and tested to the Code requirements:

Valve P&ID & coordinates E11-F010 D-25025 SH-1B (D-8) l D-2525 SH-1B (D-8)

E41-F052A D-25025 SH-1A (E-8) 0-2525 SH-1A (E-8)

E41-F052B D-25026 SH-2A (D-1)

D-2526 SH-2A (D-1)

E11-F078 D-25026 SH-2A (C-7) 0-2526 SH-2A (C-7)

E11-F079 D-25026 SH-2A (C-7) 0-2526 SH-2A (C-7)

K. Reactor Water Cleanup System

1. How is valve G31-F039 verified to close quarterly?

L. Reactor Core Isolation Cooling System l

l l -

1. Would failure of valve E51-F007 in the closed position during quarterly testing render an entire safety system inoperable?

l 5

l

2. How are valves E51-V72 and 73 individually verified to close quarterly?

3. How is valve E51-V88 verified to full-stroke open quarterly?

4 How is the stroke time measured while exercising valves E51-V8 and -V9 quarterly?

5. Provide a more detailed technical justification for not full-stroxe exercising valves E51-F001 and 002 to the closed position quarterly.

6. How is valve E51-021 verified to full-stroke open quarterly?

7. How is' valve E51-030 verified to full-stroke open quarterly?

8. Review the safety-related function of the following. valves to determine if they should be included in the IST program and tested to the Code requirements:

Valve P&ID & coordinates E51-F011 D-25029 SH-1 (F-4)

D-2529 SH-1 (F-4)

E51-F046 D-25029 SH-1 (B-4)

D-2529 SH-1 (B-4)

E51-F047 D-25029 SH-2 (E-6)

D-2529 SH-2 (E-6)

E51-F063 D-25029 SH-2 (B-8)

D-2529 SH-2 (B-8)

E51-F064 D-25029 SH-2 (B-8)

D-2529 SH-2 (B-8)'

M. Service Water System

1. Are valves SW-V136, 137, 138, and 139 fail-safe tested in accordance with the Code requirements?

6

U

, *1

2. Review the safety-related function of the following valves to ]

determine if they should be included in the IST program and tested to the Code requirements:

Valve P&ID & coordinates ,

i E11-F068A D-25037 SH-1 (D-1)  !

D-2537 SH-1 (D-1) i i

E11-F068B D-25037 SH-2-(D-8)

D-2537 SH-2 (D-8) j E11-F073 D-25037 SH-2 (C-2)

D-2537 SH-2 (C-2) i i

I 1-E11-V124 D-25037 SH-2 (B-6)

?

N. Standby Liquid Control System

1. How are valves C41-F033A and B verified to full-stroke open during quarterly testing?

1 l

0. Fuel Pool Cooling and Filtering System I

1. How are valves G41-V8 and V24 verified to close during quarterly exercising?

l l

P. Instrument Air Supply System

1. Provide a more detailed technical justification for not verifying closure of the check valves identified in valve relief request VR-11 during cold shutdowns. 1

2. The P&ID sheet identification is incorrect for valves 2-RNA-5261 and -$262 in the Valve Tables.

3. Provide a more detailed technical justification for not verifying closure of the check valves identified in valve cold shutdown justification VC-09 quarterly?

7

-l Q. Containment Atmosphere Monitoring System

1. Provide a more detailed' technical justification for not exercising valves CAC-SV1225B and 3440 quarterly during power operation. (See valve cold shutdown justification VC-10)

R. Standby Gas Treatment System

1. Is remote position indication verified for valves ?3T-V8 and 9 as required by the Code?

S. Diesel Generator Starting Air System

1. Should relief request VR-13 be referenced on page 5 of the Unit 2 Valve Tables? ,

l

2. How are the diesel generator starting air solenoid valves individually verified to full-stroke exercise quarterly?

3. How are the following valves verified to shut quarterly?

2-DSA-V141 2-DSA-V145 2-DSA-V149 2-DSA-V153 2-DSA-V142 2-DSA-V146 2-DSA-V150 2-DSA-V154

4. Review the safety-related function of the following valves to determine if they should be included in the IST program and tested in accordance with Section XI.

Valve P&ID & coordinates PRV-1689 D-2265 SH-1A (E-5)

PRV-1691 D-2265 SH-1A (E-5)

PRV-1675 D-2265 SH-1B (E-5)

PRV-1676 D-2265 SH-1B (E-5)

PRV-1664 D-2266 SH-2A (E-5)

PRV-1665 D-2266 SH-2A (E-5)

PRV-786 D-2266 SH-2B (E-5)

PRV-789 D-2266 SH-28 (E-5) 8 1

e

2. PUMP TESTING PROGRAM ,

1. How are the standby liquid control pumps tested quarterly if they ,

are required to remain aligned to the control tank during plant operation (See pump relief request PR-03)?

2. How is individual pump flow rate measured during quarterly testing of the service water pumps?

l

3. Has the service water lubricating system deactivation been completed or is it still scheduled to be completed in late 1987?

Does pump relief request PR-05 apply to these pumps or does Code

- Exception Number 4?

4. In reference to the diesel fuel oil transfer pumps, the NRC staff position is that lack of installed instrumentation is not an acceptable long term justification for not measuring the Code required parameters on pumps that perform a safety-related j function. The Unit 2 Code Exception Number 3 implies that modifications are in progress to permit testing to comply with ]

this position. Is this true and, if so, when will the modification be completed?

5. Are lubricant pressures or levels observed during pump testing for all pumps in the Brunswick IST program? If not, provide the specific technical justification for not doing so.

1 I

i l

9

o MEETING NOTICE DISTRIBUTION tDocket File NRC PDR Local PDP PD21 r/f T. Murley/J. Sniezek F. Miraglia S. Varga G. Lainas E. Sylvester W. Lanning OGC-Bethesda E. Jordan J. Partlow ACRS (10) i GPA/PA V. Wilson B. Kolostyak H. Shaw l

t o- ----- -