ML17352B258

LER 94-007-00:on 940224,station Procedure for Testing Reactor Trip Bypass Breakers Did Not Satisfy Ts.Caused by Inadequate Procedure Preparation & Review.Surveillance Procedure Enhancement Program underway.W/940325 Ltr

ML17352B258
Person / Time
Site:	South Texas
Issue date:	03/25/1994
From:	Groth J, Pinzon J HOUSTON LIGHTING & POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-94-007-01, LER-94-7-1, ST-HL-AE-004737, ST-HL-AE-4737, NUDOCS 9404050194
Download: ML17352B258 (7)

Text

FLORIDA POWER 8r LIGHT COMPAiVY April 2, 1984 L-84-90 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regul atory Commi ssion Washington, D.C. 20555

Dear Mr. Ei senhut:

Re: Turkey Point Units 3 8 4 Docket No. 50-250, 50-251 Proposed License Amendment Inservice Ins ection and Inservice Test Pro ran In accordance with 10 CFR 50.90, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to anend Appendix A of Facility Operating Licenses DPR 31 and DPR 41.

This amendment is submitted as required by 10 CFR 50.55a(g)(5)(ii) when our revised Inservi ce Inspection (IS I ) and Inservi ce Test ( I ST) progr aIIs conflict wi th the current techni c al speci fi cati ons. To make the techni cal specifications current, we propose to adopt the wording of the Standard Technical Specifications for Westinghouse Pressurized Water Reactors (NUREG 0452, Revision 4). This change will keep the Technical Specifications up to date with the periodic changes in the ASME Boiler and Pressure Vessel Code without the need for future license anendments. This submittal is being made concurrently with the submittals of the ISI Second Ten-Year Summary and a revision to the Inservice Test PrograII for Pumps and Valves for Turkey Point Units 3 5 4.

The proposed anendment is described below and shown on the accompanying techni cal speci fi cati on pages.

Pa e 3.3-1 Specification 3.3.3 is revised to delete specifics of isolation valve testing. Testing of these valves is included in the Inservice Test Progran for Pumps and Valves which is addressed in proposed Specification 4.0.3.

S46 4050-VP4-840402 05000250 PDR ADOCK P ~ PDR PEOPLE... SERVING PEOPLE

Office of Nuclear Reactor Regulation Attention: Nr. Oarrell G. Eisenhut, Oirector Page 2 Pa e 3.4-2 Specifications 3.4.l.b.2 and b.4 are revised to delete operable safety injection and residual heat removal pump testing prior to maintenance on inoperable pumps. Testing of these components is included in the Inservice Test Progran for Pumps and Valves which is addressed in proposed Specification 4.0. 3.

Page 3.4-2a Specifications 3.4.1.b.5 and b.6 are revised to delete testing of duplicate function valves and to add a requirement to verify that the remaining residual heat removal heat exchanger and duplicate function valves meet the requirements of proposed Specification 4.0.3.

Pa e 3.4-4 Specifications 3.4.2.b.2 and b.3 are revised to delete operable containment spray pump and valve testing prior to maintenance on inoperable items. These pumps and valves are included is the Pump and Valve Test Progran.

Specification 3.4.3.b.2 is revised to delete operable containment filter valve testing prior to maintenance on inoperable valves. These valves are included 0 in the Pump and Valve Test Progran.

Pa e 3.4-5 Specification 3.4.4.b.2, 3.4.5.b.l and b.2 are revised to delete operable pump and heat exchanger testirig prior to maintenance on inoperable components.

These items are included in the ISI and IST Prograns. Requirements are added to verify that component cooling water pumps and heat exchangers and intake cooling water headers and pumps that remain operable, when other components are inoperable, meet the requirements of proposed Specification 4.0.3.

Pa e 3.4-6 Specification 3.4.6.b.2 is revised to delete testing of operable duplicate function valves.

Pa e 3.8-1 Specification 3.8.1d and 3.8.4 are revised to specify testing in accordance wi th Specifications 4.0. 3 and 4. 40.

Page 4.0-1, -2 4.1-1 Specification 4.0.3 is provided to add the inservice inspection and testing requirements of the ASME Code. Editorial changes are made to page 4.1-1 to facilitate this change.

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Office of Nuclear Reactor Regul ation Attention: Mr. Darrell G. Eisenhut, Director Page 3 Table 4.1-2 Sheet 2 of 3 This table is revised to require testing of pressurizer and main stean safety valves in accordance with Specification 4.0.3.

Pa e 4.2-1, -2, and Table 4.2-1 This specification is revised to remove requirements which are addressed oy proposed Specification 4.0.3. Those items formerly in Table 4.2-1 which were not addressed in proposed specification 4.0.3 are placed in the specification as items 4.2.3 and 4.2.4.

Pa e 4.4-2 An editorial change is made to the specification referenced in the acceptance cri teri a.

Pa e 4.4-3 Specifications 4.4.3 and 4.4.4 are revised to reference Specification 4.0.3 for containment isolation valves and delete the specific requirements for inservice testing of portions of the residual heat removal system. These items are included in the Inservice Test Progran for Pumps and Valves, which is addressed in proposed Specification 4.0.3.

Pa e 4.5-1 Specification 4.5 is rev'ised by deleting the surveillance specification for safety injection pumps and valves and inserting a reference to the testing required by proposed Specification 4.0.3.

P a e 4.6-2 Specification 4.6.2 is revised to delete the testing requirements for containment spray pumps and motor operated isolation valves. These items are inciuded in the Inservice Test Progran for Pumps and Valves which is addressed in proposed Specification 4.0.3.

Pa e 4.7-3 Revisions are made to post accident containment vent system valve testing to refer to Specification 4.0.3.

Specification 4.9 i s revised to adopt standard Techni cal specification wording

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for testing of the Main Steaa Isolation Valves. These valves are included in the Inservice Test Progran for Pumps and Valves, which is addressed in proposed Specification 4.03.

Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Page 4 0 Pa e 4.10-1 Specification 4.10 is revised to reference Specification 4.0.3 for testing of auxiliary feedwater pumps and valves.

Pa e B4.0-1 B4.2-1 The bases for Specification 4.0 and 4.2 are revised.

Pages i through vi, 3.4-3, 3.8-2, 4.2-2 through 4.2-6, 4.7-4 and B4.2-2 are provided with appropri ate changes to Table of Contents or page numberings to be consistent with the above changes.

In accordance with 10 CFR 50.91(a) (I), it has been determined that the proposed amendment does not involve any significant hazards considerations pursuant to 10 CFR 50.92. The No Significant Hazards Considerations determination i s attached.

In accordance with 10 CFR 50.91(b)(I) a copy of the proposed anendment is being forwarded to the State Designee for the State of Florida.

The proposed anendment has been reviewed by the Turkey Point Pl ant Nuclear Saety Committee and the Florida Power 5 Light Company Nuclear Review Board.

The proposed anendment has been determined to be a Class I and II amendment, and in accordance with 10 CFR 170.22, a check for $ 1,600.00 will follow by separate letter.

Very truly yours, J. W. Willians, Jr.

Vice President Nuclear Energy JWW/PLP/js Attachment CC: J. P. O'ei ly1 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Mari et t a Street, N.W., Sui te 2900 Atl anta, GA 30303 Lyle E. Jerrett, Administrator Radiological Health Ser vices Dept. of Health 8 Rehabilitative Services 0 1323 Wi newood Tal l ahassee, Boulevard Fl ori da Harold F. Reis, Esquire 32301 P NS-L I-84-116

STATE OF FLORIDA )

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COUNTY OF DADE J. W. WilliaIIs, Jr., being first duly sworn, deposes and says:

1 That he is Vice President of Florida Power & Light Company, the licensee herei n; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.

. Williams, Jr.

t Subs ribed day and sworn of to before me this

, 1984.

NOTARY PUB'C, in and for the County of Dade, State of Florida.

AOTARY 'PUSUC STATs CF FlORIDA gY CGM!AISS IGN EXPIRH PER 12 1987 My commi ssi on expires: I DED THR'J,w:~~ I".'5'.LvlcE UND