ML20214N797

Forwards Request for Addl Info for Review of 850627 Submittal Re Inservice Testing at Facility.Addl Info Should Be Submitted within 60 Days of Ltr Receipt

ML20214N797
Person / Time
Site:	Millstone
Issue date:	05/27/1987
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Mroczka E NORTHEAST NUCLEAR ENERGY CO.
References
TAC-59265, NUDOCS 8706030078
Download: ML20214N797 (8)

Text

1 May 27, 1987

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[Q Docket No. 50-336

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Mr. Edward J. Mroczka Senior Vice President Nuclear Engineering and Operations

-Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06141-0270

SUBJECT:

MILLSTONE NUCLEAR STATION, UNIT NO. 2 (TAC #59265)

We are in the process of reviewing your June 27, 1985 submittal concerning inservice testing at Millstone Unit 2.

In order to expedite our review, we request that you respond to the enclosed questions within 60 days from receipt of this letter.

This request for additional information affects fewer than 10 respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely,

/s/

David H. Jaffe, Project Manager Project Directorate I 4 Division of Reactor Projects I/II

Enclosure:

Request for Additional Information cc w/ enclosure:

See next page Docket File NRC & Local PDRs PD I-4 Reading SVarga BBoger SNorris i

DJaffe OGC-Bethesda E. Jordan J. Partlow ACRS (10)

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{ / /87 8706030078 870527 "

DR ADOCK 05000336 PDR:

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9 Mr. John F. Opeka Millstone Nuclear Power Station Northeast Nuclear Energy Company Unit No. 2 cc:

Gerald Garfield, Esq.

Mr. Wayne D. Romberg Day, Berry & Howard Superintendent Counselors at Law Millstone Nuclear Power Station R

City Place P. O. Box 128 Hartford, Connecticut 06103-3499 Waterford, Connecticut 06385 Regional Administrator, Region I Mr. Edward J. Mroczka U.S. Nuclear Regulatory Comission

.Vice President, Nuclear Operations Office of Executive Director for Northeast Nuclear Energy Company Operations P. O. Box 270 631 Park Avenue Hartford, Connecticut 06141-0270 King of Prussia, Pennsylvania 19406 Mr. Charles Brinkman, Manager Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.

7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. Lawrence Bettencourt, First Selectman Town of Waterford Hall of Records - 200 Boston Post Road 4

Waterford, Connecticut 06385 Northeast Utilities Service Company ATTN: Mr. Richard R. Laudenat, Manager Generation Facilities Licensing Post Office Box 270 Hartford, Connecticut 06141-0270 i

Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection State Office Building Hartford, Connecticut 06106 Mr. Theodore Rebelowski 3

U.S. NRC P. O. Box 615 Waterford, Connecticut 06385-0615 Office of Policy & Management ATTN: Under Secretary Energy Division 80 Washington Street Hartford, Connecticut 06106 l

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U MILLSTONE NUCLEAR p0WER STATION, UNIT 2 pVMP AND VALVE INSERVICE TESTING PROGRAM REVIEW REQUEST FOR ADDITIONAL INFORMATION I.

Valve Testing program A.

General Questicqs_.and Comments 1.

Provide a list of all valves that perform both a containment isolation function and a pressure boundary isolation function and that are not leak rate tested to both the Appendix J and Section XI requirements.

2.

Provide a list of all valves that are Appendix J, Type C, leak rate tested that are not included in the IST program and b

categorized A or A/C?

3.

Provide the limiting value of full-stroke time for all power operated valves in the IST program for the staff's review.

4.

The NRC has concluded that the applicable leak test proceedures and requirements for containment isolation valves are determined by 10 CFR 50 Appendix J, however, the licensee must comply with the Analysis of Leakage Rates and Corrective Action Requirements Paragraphs of Section XI, IWV-3426 and -3427.

5.

Valves whose test frequency is required to be increased to once each month as required by IWV-3417 and which can only be tested during cold shutdowns or refueling outages shall be repaired before plant startup.

6.

All valves with remote position indicators shall be observed at least ace every 2 years to verify that valve operation is accurately indicated as per IWV-3300.

1 J

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3-B. - Spent Fuel ' Pool Cooling System 1.

How are check valves 2RW-67~and~222 verified to close?

i C.

Main Steam System 1.

How are valves 2-MS-4A and 48 verified to full-stroke open quarterly? How are these valves verified to close-quarterly?

l 2.

Provide a more specific technical justification for not full-stroke exercising valves-2-MS-65A and 65B quarterly.

.3.

Provide a more specific technical justification for not full-stroke exercising valves'2-MS-190A and 1908 quarterly.

4.

Review the safety function of valves 2-MS-1A and IB (P&ID i

location J-7 and D-9) to determine if they should be included in the IS~ program.

)

D.

Containment Spray System i

1.

The NRC staff has determined that the air flow / audible test I

method of verifying the full-stroke capability of check valves is not acceptable, therefore, an alternate means of verifying full-stroke capability of valves 2-CS-5A and 5B must be l

identified.

I 2.

Provide a more specific technical justification for not i

full-stroke exercising valves 2-CS-13.1A and 13.1B quarterly, i

3.

Provide a more specific technical justification for not L

full-stroke exercising valves 2-CS-15A and'15B during cold f.

shutdewn or each refueling outage.

i 2

t

t E.

Safety Injection System 1.

How are valves 2-SI-215, 225,'235, and 245 full-stroke exercised during= refueling outages?

2.

How are valves 2-SI-217, 227, 237, and 247 full-stroke exercised during cold shutdowns?

3.

Evaluate the use of the six inch SI and containment spray test-line to the RWST to full-or partial-stroke exercise valves 2-51-434 and 446 quarterly during power operation.

4.

What is the "ET" test requirement as identified for valves 2-51-614, 624, 634, and 6447 5.

Provide the relief request or' cold shutdown justification pertaining to valves 2-51-618, 628,'638, and 648.

6.

Provide a list of valves that are leak rate' tested as reactor coolant system pressure boundary isolation valves.

7.

Describe any hot leg injection method that is used for long term recirculation post LOCA at Millstone Unit 2.

j 8.

Review the safety function of valves 2-SI-662 and 663 to determine if they should be included in the IST program.

F.

Feedwater Systems 1.

Although the valve operator is not directly connected to the-valve obturator for 2-FW-5A and 58, discuss the reasons for not exercising the obturator during cold shutdowns or refueling outages. What is the safety function of these valves in the open I

position?

i 2.

What is the safety function of valves 2-FW-12A and B in the l

closed position?

1 3

l

i 3.

Why is the stroke time not measured during the quarterly testing of valves 2-FW-43A, B, and 44?

4.

Describe any credit taken in the safety analysis for the emergency water supply from the fire water system to the auxiliary feedwater system.

5.

' Describe any credit taken in the safety analysis for the auxiliary feedwater supply to the spent fuel pool.

G.

Reactor Building Cotponent Cooling Water System

. 1.

Why were valves 2-RB-30.1A, B, and 2-RB-37.2A and B categorized A and no leak rate test identified for these valves?

b H.

Chemical and Volume Control System 1.

Why are both valves 2-CH-518 and 519 required to be open at all times during power operation?

2.

Review the safety function of valves 2-CH-118, 132, 191, and 431 (p&ID locations F-9, E-8, E-9, and J-13) to determine if they shouldbeinciudedintheISTprogram.

I.

Reactor Coolant System 4

1.

If valves 2-RC-402 and 404 are used for low-temperature overpressure protection of the reactor coolant system during

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t shutdowns, these valves must be categorized B/C and be exercised during cold shutdowns and refueling outages.

2.

Provide a more specific technical just.ification for not full-stroke exercising the reactor vessel and pressurizer vent valves during cold shutdowns.

4

'O

• 4 1

J.

Containment Isolation System 1.

Provide the P&ID that shows valve 2-AC-51.

2.

Provide the request for relief for the valves in the containment isolation system that have a fail-safe test during cold shutdown (FTCS) as identified in the testing alternative column of the valve table.

3.

What specific cod? requirement is relief requested from in containment isol. lon system relief request no. 4 and for which valves does this relief request apply?

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l b

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4 5

II. pump Testing program 1.

How is inlet pressure and pump flowrate measured for the service water pumps?

2.

The NRC staff agrees that pump vibration monitoring utilizing pump vibration velocity rather than pump vibration displacement can provide more useful information for evaluation of pump degradation, however the acceptance criteria in the Millstone Unit 2 IST program is not acceptable to the staff because there are no absolute limiting values in the acceptance criteria. The acceptance criteria as defined in ASME OM6, Inservice Testing of Pumps, draft 8 provides one acceptance

. criterion for vibration velocity testing whicn is acceptable to the staff.

5 3.

Table IWP-3100-1 requires the measurement of both pump differential pressure and flowrate for each pump identified in the IST program irrespective of fixed resistance or variable resistance flowpaths.

How can the pump differential pressure and'flowrate be measured for the auxiliary feedwater, safety injection, containment spray, charging, and boric acid pumps?

4.

Do the charging pumps have a variable speed coupling between the pump L

and the motor requiring measurement of pump shaft speed as required by IWP-44007 5.

Is pump shaft rotational speed measured for the turbine driven auxiliary feedwater pump?

6.

How is inlet pressure measured for the boric acid pumps?

i 6

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