ML17346A246
| ML17346A246 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 04/02/1984 |
| From: | Williams J FLORIDA POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17346A247 | List: |
| References | |
| L-84-90, NUDOCS 8404050194 | |
| Download: ML17346A246 (8) | |
Text
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REGULATOR)
NFORMATION DISTRIBUTION S EM (RIDS)
ACCESSION NOR:8004050194 DOC ~ DATE'4/00/02 NOTARIZED:
YES DOCKET 0
FACIL:50 250 Turkey Point Planti Unit 3i Florida Power and Light C
05000250 50-251 Turkey Point Planti Unit 4i Florida Power and Light C
05000251 AUTH BYNAME AUTHOR AFFILIATION NILLIAMSiJ ~ 1'].
Florida Power 8 Light Cos REC IP, NAME.
REC IP IENT AFFILIATION EISENHUTiD,G, Division of Licensing
SUBJECT:
Application for amend to License DPR 31 8 DPR-01ir evising Tee)i Specs re inservice insp 3 inservice test
- program, DISTRIBUTION CODE:
AOATS COPIES RECEIVED:LTR J ENCL J SIZE: a W l TITLE; OR Submittal: Inservice Inspection/Testing NOTES:
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y( 4 FLORIDAPOWER & LIGHT COMPANY April 2, 1984 L-84-90 Office of Nuclear Reactor Regulation Attention:
Nr. Darrel 1 G ~
Ei senhut, Director Division of Licensing U ~ S ~ Nuclear Regul atory Commission Washington, D ~ C ~
20555 Dear Hr.
Ei senhut:
Re:
Turkey Point Units 3 5 4 Docket No. 50-250, 50-251 Proposed License Amendment Inservi ce Ins ection and Inservi ce Test Pro ran In accordance with 10 CFR 50 ~ 90, Florida Power 5 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 ~
Thi s amendment is submitted as required by 10 CFR 50 ~ 55a(g) (5) (ii ) when our revised Inservi ce Inspection (ISI
)
and Inservi ce Test (IST) progr ans conflict wi th the current techni c'al speci ficati ons.
To make the techni cal specifications
- current, we propose to adopt the wording of the Standard Techni cal Specifications for Westinghouse Pressurized Water Reactors (NUREG,
- 0452, Revision 4) ~
This change will keep the Technical Speci ficati ons 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 submi ttal s of the ISI Second Ten-Year Summary and a
revision to the Inservi ce Test Prog ran for Pumps and Valves for Turkey Point Units 3 5 4 ~
The proposed anendment is described below and shown on the accompanying techni c al speci fi c ati on p ages
~
Page
- 3. 3-1 Specification 3.3. 3 is revised to delete specifics of isolation valve testing.
Testing of these valves i s included in the Inservi ce Test Program for Pumps and Valves which is addressed in proposed Specification 4 ~ 0 ~ 3.
l8404050194 84040P
">'DR ADOCK 05000250 PEOPLE... SERVING PEOPLF
Office of Nuclear Reactor Regul ation Attention:
Mr. Darrell G. Eisenhut, Director 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 val ves are included i s the Pump and Val ve Test Prog ran.
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 in the Pump and Valve Test Program.
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 testing 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.
Page 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.ld and 3.8.4 are revised to specify testing in accordance with Specifications 4.0.3 and 4.10.
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.
Office of Nuclear Reactor Regulation 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.
Page 4.2-1, -2, and Table 4.2-1 This specification is revised to remove requirements which are addressed by 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 criteri 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 revised by deleting the surveillance specification for'afety 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 included 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.
Pa e 4.9-1 Speci ficati on 4. 9 i s revi sed to adopt st and ard Techni cal speci fi cati on wordi ng for testing of the Main Stean Isolation Valves.
These valves are included in the Inservice Test Progran for Pumps and Valves, which is addressed in proposed Speci ficati on 4.03.
Office of Nuclear Reactor Regulation Attention:
Mr. Darrell G. Eisenhut, Director Page 4
Pa e 4.10-1 Specification 4.10 is revised to reference Specification 4.0.3 for testing of auxili ary feedwater pumps and valves.
Page 84.0-1 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 84.2-2 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 determi n ati on i s att ached.
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 Plant 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, C
~
J.
W. Williams, Jr.
Vice President Nuclear Energy JWW/PLP/js Attachment CC:
J.
P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W., Suite 2900
- Atlanta, GA 30303 Lyle E. Jerrett, Administrator Radiological Health Services Dept. of Health 5 Rehabilitative Services 1323 Winewood Boul evard Tal l ahassee, Fl ori da 32301 Harol d F.
Rei s, Esqui re P NS-LI-84-116
STATE OF FLORIDA
)
COUNTY OF DADE SS ~
J.
W. Willians, Jr., being first duly sworn, deposes and says:
That he is Vice President of Florida Power 8 Light Company, the licensee herein; 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 Li cen see.
J.. Williams, Jr.
Subs ribed and sworn to before me this day of fl4
, 1984.
ROTARY PU8LIC STATE OF FLORIDA rMY COMM(SS ION EXPIRES FEB 12 1987 ONDED THRU GENERAL INSURANCE UND My commission expires:
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, NOTPR) PJBLIC, in and for the County of
- 0'ade";.-St'ate of Florida.
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