ML17348B350

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Concludes That Extending Relief Period Until 920831 for Reliefs VR-2,VR-6,VR-9,VR-11,VR-12,VR-13 & VR-14 Appropriate.Interim Relief Granted for VR-29,VR-30,VR-31 & VR-32
ML17348B350
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 01/23/1992
From: Berkow H
Office of Nuclear Reactor Regulation
To: Goldberg J
FLORIDA POWER & LIGHT CO.
References
GL-89-04, GL-89-4, TAC-M82373, TAC-M82374, NUDOCS 9201300274
Download: ML17348B350 (6)


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Docket Nos.

50-250 and 50-251 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555 January 23, 1992 Hr. J.

H. Goldberg President Nuclear Division Florida Power 5 Light Company Post Office Box 14000 Juno

Beach, Florida 33408-0420

Dear Hr. Goldberg:

SUBJECT:

TURKEY POINT UNITS 3 AND 4 INTERIM RELIEF FROM THE INSERVICE TESTING PROGRAM FOR PUMPS AND VALVES (TAC NOS.

H82373 AND M82374)

On October 3,

1989, you submitted your response'o Generic Letter 89-04.

Your submittal consisted of a review of your Inservice Testing (IST) Program for.

the second 10-year interval, along with several requests for relief from the" ASHE Pressure Vessel Code Section XI requirements.

The staff's Safety Evaluation (SE) was transmitted to you on September 20,

1991, and provided a.:

summary tabulation of our conclusions concerning each relief request.

Your letter of December 31, 1991, resubmitted relief requests VR-2 (AFW to steam generator supply valves:

CV-*-2816 thru -2818 and CV-*-2831 thru

-2833),

VR-6 (charging pump to boron injection valve:

HCV-*-0121), VR-9 (containment spray header check valves:

3(4) 0890A and -0890B), VR-ll (SI hot leg injection check valves:

3(4) -0874A and -0874B),

VR-12 (SI cold leg injection check valves:

3(4) -0875A, -0875B, and -0875C),

VR-13 (SI accumulator discharge check valves:

3(4) -0875D, -0875E, and -0875F),

and VR-14 (RHR cold leg injection check valves:

3(4) -0876B and -0876C).

Your letter requested an extension of these reliefs.

You also requested the following new reliefs:

VR-29 (AFW pump check valves:

AFWU 3-0017 and 4-0016),

VR-30 (boric acid pumps to charging pump check valves:

3(4) -0351 and 3(4) -0397 A 8 B), VR-31 (main steam check valves:

3(4)10-004 thru

-006),

and VR-32 (fuel oil transfer pump check valves:

SV-4-3434 A 5 B).

The relief requests VR-2, VR-6, VR-9, VR-ll, VR-12, VR-13 and VR-14 were previously reviewed by the staff and the evaluation is contained in staff's SE dated September, 20, 1991.

The staff's preliminary review of the information related to these relief requests provided in your letter of December 31, 1991 indicates that'.the relief requests, as yet, do not fully address the conclusions of the staff's SE.

However, based on the staff's preliminary review of the resubmitted relief requests and discussions during the telecon of December 18, 199!., the staff agrees that additional time is required to fully address those conclusions and develop suitable alternative surve'.llance techniques.

In the interim, the proposed alternative testing as evaluated by the staff and transmitted to you on September 20, 1991, provides an acceptable 920i300274 920i23 PDR ADOCK,05000250

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Mr. J.

H. Goldberg January 23, 1992 level of quality and safety for these valves, pursuant to 10 CFR 50.55a(a)(3)(i).

Therefore, an extension of the period of relief is appropriate through August 31, 1992.

With respect to new relief requests VR-29, VR-30, VR-31, and VR-32, your letter indicates that compliance with ASME Code Section XI IWV 3520 requirements is impractical.

The Code requires that these valves be exercised at least once every 3 months during normal plant operation or when the plant is in a cold shutdown mode.

For VR-29 and VR-30, it is impractical to comply with the Code, since currently there is no instrumentation available to verify flow in the lines.

The valves included in VR-31 are large stop check valves in the main steam lines leading to the main turbine generator.

Presently, there is no practical way of verifying closure of these valves by a reverse flow test, and during plant operation at power, closure of these valves would result in a severe transient on the plant.

The valves covered under the relief request VR-32 were installed during the recently completed dual-unit outage.

These valves open to provide flow paths for diesel fuel oil from the fuel oil transfer pumps to the respective day tanks.

These are totally enclosed solenoid valves having no local or remote position indication, thus measuring an accurate stroke time is impractical with the current design.

The proposed alternative testing includes part-stroking during plant operation, disassembly and inspection of valve components during a refueling outage, partial flow testing after reassembly, and use of a handwheel during cold shutdown.

The staff's preliminary review indicates that the proposed alternative testing provides reasonable assurance of the operational readiness of these valves, and pursuant to 10 CFR 50.55a(g)(6)(i),

an interim relief is appropriate until the staff completes its review, or by August 31,

1992, whichever comes first.

The relief requests involving disassembly, inspection, and manual exercising of the valves, as stated in your December 31, 1991 letter, are considered short-term alternative testing proposals which should be replaced by alternative surveillance techniques, such as non-intrusive diagnostics.

In the interim, you should evaluate means of inservice testing of valve performance other than employing a disassembly and inspection program.

If no other means, including non-intrusive diagnostics, can be utilized, you will need to request a specific relief for each individual valve, or group of similar valves.

You will also be required to describe the reasons why no other means;.of. inservice testing are available.

Further, as part of the short-term aTternative testing proposal, you must include requirements to verify, prior to reassembly, the cleanliness and prope'r orientation of each valve.

In your letter of December 31, 1991, you also requested extending the inspection interval to 10 years for groups of-identical valves used in similar applications (VR-12, VR-13, VR-14) based on historical data and experience.

The staff's preliminary review indicates the bases provided are inconsistent and incomplete and therefore, cannot be used to justify the proposed interim extension.,

Therefore, on the basis of the information reviewed, the request for extending the inspection interval for these valves to 10 years is denied.

Hr. J.

H. Goldberg January 23, 1992 The staff has determined that extending the relief period until August 31, 1992 for reliefs VR-2, VR-6, VR-9, VR-ll, VR-12, VR-13, and VR-14, is appropriate and, in the interim, the proposed alternative testing will provide an acceptable level of quality and safety pursuant to 10 CFR 50.55a(a)(3)(i).

In addition, interim relief is granted for relief requests VR-29, VR-30, VR-31, and VR-32 pursuant to 10 CFR 50.55a(g)(6)(i),

in that the Code requirements are impractical and that the granting of the relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.

These reliefs are granted until the staff's detailed review is completed or until August 31, 1992, whichever comes first.

Sincerely, s/

erbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation cc:

See next page

~OI TRI N

Docket Filets'RC 8, Local PDRs PDII-2 RDG T. Hurley/F. Hiraglia J. Partlow C. Rossi J.

Lieberman S.

Varga G. Lainas H. Berkow R. Auluck D. Hiller OGC E. Jordan G. Hill (4 cpys. for each Docket ¹)

ACRS (10)

GPA/PA SECY (ORDERS ONLY)

OC/LFHB J. Wechselberger,

EDO, 17-G-21 H. Sinkule, RII
  • See previous concurrence

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Mr. J.

H. Goldberg Florida Power and Light Company Turkey Point Plant CC:

Harold F. Reis, Esquire Newman and Holtzinger, P.C.

1615 L Street, N.W.

Washington, DC 20036 Jack Shreve, Public Counsel Office of the Public Counsel c/o The Florida Legislature 111 West Madison Avenue, Room 812 Tallahassee, Florida 32301 John T. Butler, Esquire

Steel, Hector and Davis 4000 Southeast Financial Center
Miami, Fl orida 33131-2398 Mr. Thomas F. Plunkett, Site Vice President Turkey Point Nuclear Plant Florida Power and Light Company P.O.

Box 029100 Joaquin Avino County Manager of Metropolitan Dade County ill NW 1st Street, 29th Floor Miami, Florida 33102 Senior Resident Inspector Turkey Point Nuclear Generating Station U.S. Nuclear Regulatory Commission P.O.

Box 1448 Homestead, Florida 33090 Mr. Jacob Daniel Nash Office of Radiation Control Department of Health. and Rehabilitative Services 1317 Winewood Blvd"."-

Tallahassee, Fl'orida 32399-0700

. Mr. Robert G. Nave, Director Emergency Management Department of Community Affairs 2640 Centerview Drive Tallahassee, Florida 32399-2100 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, N.W. Suite 2900 Atlanta, Georgia 30323 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 Plant Manager Turkey Point Nuclear Plant Florida Power and Light Company P.O.

Box 029100 Miami, Florida 33102 Mr. R.

E. Grazio Director, Nuclear Licensing Florida Power and Light Company P.O.

Box 14000 Juno

Beach, Florida 33408-0420