ML20150D818

Approves Interim Relief from Certain ASME Code Testing Requirements W/O Conditions for All Reliefs Requested by Licensee Except Two.Exceptions Granted Pending Evaluation of Compliance W/Code Requirements & Required Mods.W/Summary

ML20150D818
Person / Time
Site:	Crystal River
Issue date:	03/21/1988
From:	Berkow H Office of Nuclear Reactor Regulation
To:	Wilgus W FLORIDA POWER CORP.
References
TAC-67178, NUDOCS 8803250155
Download: ML20150D818 (6)

Text

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.a ttog'o UNITED STATES

&8" NUCLEAR HEGULATORY COMMISSION wt t

WASHINGTON, D. C. 20555 8

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March 21, 1988 Docket No.80-302 Mr. W. S. Wilgus Vice President, Nuclear Operations Florida Power Corporation ATTN: Manager, Nuclear Licensing P. O. Box 219 Crystal River, Florida 32629

SUBJECT:

INSERVICE TESTING PROGRAM - CRYSTAL RIVER I! NIT 3 APPROVAL OF RELIEF RE0 VESTS (TAC NO. 67178)

By letter dated December 31, 1987 Florida Power Corporation submitted its updated Inservice Testing (IST) Program Plan (program) for the second 10-year interval at Crystal River Unit 3 (CR-3).

The IST program is required by 10 CFR 50.55a to comply with the ASME Boiler and Pressure Vessel Code,Section XI, j

1983 Edition through the Surimer 1983 Addenda.

Pursuant to 10 CFR 50.F5a(g)(5),

you have requested relief from certain ASME Code testing requirements which 1

are impractical within the limits of design and plant operational requirenents.

The recuest for relief includes an explanation and justification for the relief and a proposal for alternative test procedures.

The relief reouests included l

in the submittal were reviewed by the staff and were the subject of a working meeting on February 26, 1988.

Based on the agreements and resolutions reached during that meeting, you submitted revised relief requests on March 10, 1988 j

We have perfomed an interim evaluation of the CR-3 IST program relief requests which is intended to provide an assessment of the program until a final safety evaluation (SE) o' the prooram is completed.

Our preliminary evaluation has identified no inconsistencies or objections to your requests and we have therefore determined that an interin period of relief is appropriate until we can fully complete our assessment.

Based on our evaluation, interim relief is granted without conditions for all reliefs requested by the licensee except i

two.

For these exceptions (V-111, Y-370), interim relief is granted pending evaluation of the extent to which plant desigr. allows compliance with the Code requirements and required modifications.

A sumary of the results of our review is presented in Table 1 (enclosed).

Since this approval does not represent the results of the final program review, issuance of the 'inal SE upon completion of our review of the program could identify corponents that should be added to the program. The relief granted herein will terminate upon issuance of the final SE, which will then supersede this document.

8803250155 080321 PDR ADOCK 05000302 O

PDR

A0NR 211988-Mr. W. S. Wilgus For the reliefs granted, we have determined that the ASME Code Section XI requirements are impractical and that, pursuant to 10 CFR 50.55a(g)(6)(i),

the reliefs are authorized by law and will not endanger life or property or the'.

conson defense and security and is otherwise in the public interest, giving due consideration to the burden on the licensee that could result if the reauire-nents were imposed on the facility.

Sincerely, L

Original signed by Herbert N. Perkow, Director Pro.iect Directorate II-2 Division of Reactor Projects-l/II Office of Nuclear Reactor Regulation Er. closure:

As stated cc w/ enclosure:

See next page DISTRIBUTION EN3 H. Silver NRC A local PORs OGC-WF PDII-2 R/F E. Jordan S. Varga J. Partlow G. Lainas ACRS (10)

D. Miller Gray File T. Sullivan l

vious concurrences

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I TABLE 1 Crystal River 3 Summary of Relief Requests Relief Request Component Relief Alternate NRC Number ID Requested Test Action V-030 BSV-26 IWV-3521 &

Sample Relief BSV-27 IWV-3522(b) disassembly Granted and inspection at refueling V-111 EFP-1 &

IWP-3100 To be determined Interim EFP-2 Relief Granted until end of next refueling outage i

V-112 DFP-1A, 18 IWP-3100 Calculate flow Relief DFP-1C 10 by measuring Granted l

change in day

)

tank volume V-115 All Class 1 IWV-3512 Use IWV-3512 Relief 2, 3 relief Test Code ANSI /ASME Granted valves 25.3, 1976 OM-1 i

V-120 BSV-150 IWV-3520 Sample dis-Relief 151 assembly and Granted inspection at refueling l

I

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- Relief Request Component Relief Alternate NRC Number 10 Requested Test Action V-128 CFV-1 IWV-3522(b)

Sample Relief CFV-3 disassembly Granted and inspection at refueling

)

V-129 CFV-2 IWV-3522(b)

Sample Relief CFV-4 disassembly Granted and inspection 1

at refueling l

V-131 DJV-1,2 IWV-3521 Partial stroke Relief DJV-17, 18 quarterly and Granted full cor.tinuous load test at Refueling V-132 DJV-27,28,29 IWV-3521 Same as V-131 Relief DJV-30,31,32 above Granted DJV-38,39 V-150 DWV-162 IWV-3521 Verify closure Relief during Appendix J Granted leak testing at refueling V-160 CFV-17, 20 IWV-3522(b)

Same as V-150 Relief above Granted V-170 CFV-18, 19 IWV-3522(b)

Same as V-150 Relief above Granted V-190 MVV-36, 37 IWV-3522 MUV-43 & 161 Relief MUV-42, 43 partial stroke Granted MUV-160, 161 exercised MVV-163, 164 quarterly. All valves full stroke at refueling

A

. Relief Request Component Relief Alternate NRC Number ID Requested Test Action V-200 MUV-60,72 IWV-3522(b)

Sample Relief disassembly Granted and inspection at refueling V-210 All power IWV-3417(a)

Declare in-Relief valves with operable if Granted stroke time stroke time

< 2 seconds exceeds 2 seconds V-320 All valves IWV-3412(a)

See Relief Relief tested IWV-3415 Request V-320 Granted during cold shutdown V-330 All valves IWV-3417(b)

Operational Relief tested IWV-3523 mode defined Gronted during cold by Tech Specs shutdown V-360 CAV-2, 431 IWV-3300 Verify remote Relief position Granted indication by indirect methods V-362 CHV-90,97 IWV-3300 Same as V-360 Relief CHV-101,108 above Granted V-364 EFU-55,56 IWV-3300 Same as V-360 Relief EFU-57,58 above Granted V-370 CHP-1A IWP-3100-1 Verify proper Interim CHP-1B performance by Relief indirect means Granted until instrumen-until end tation is in-of next stalled refueling outage

t Mr. W. S. Wilgus Cr.vstal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:

Mr. P. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. F. McKee Mr. F. Alex Griffin, Chairman Director, Nuclear Plant Operations Roard of County Commissioners Florida Power Corporation Citrus County P. O. Rox 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Mr. E. C. Simpson Babcock & Wilcox Director, Nuclear Site Nuclear Power Generation Division Florida Power Corporation Support 1700 Rockville Pike, Suite 5?S P.O. Box 219 Rockville, Maryland 20852 Crystal River, Florida 32629 Resident Inspector U.S. Nuclear Regulatory Commission 15760 West Powerline Street Crystal River, Florida 37629 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, Georgia 30323 Jacob Daniel flash Office of Radiation Control Department of Health and Rehabilitative Services 1317 Winewood Blvd.

Tallahassee, Florida 32399-0700 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 3P301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304 1