ML18088B302

St. Lucie Unit No. 1 - Proposed Supplemental Amendment to Facility Operating License DPR-67. Proposed Technical Specification Changes to Conform the Technical Specification to the Revised Program by 10 CFR 50.55a(g)(5)(ii)

ML18088B302
Person / Time
Site:	Saint Lucie
Issue date:	09/16/1977
From:	Uhrig R E Florida Power & Light Co
To:	Stello V Office of Nuclear Reactor Regulation
References
L-77-291
Download: ML18088B302 (8)

Text

P.O.BOX 013100, MIAMI, FL 33101 0-hn vA FLORIDA POWER 84 LIGHT COMPANY September 16, 1977 L-77-291 Office of Nuclear Reactor Regulat'ttn:

Mr.Victor Stello, Direct, gf/f/Division of Operating Re t rs~,f p U.S.Nuclear Regulatory Commiss'Qp Washington, D.C.20555'.s.~I977~

Dear Mr.Stello:

Re: St.Lucie Unit No.1 Docket No.50-335 Proposed Supplemental Amendment to Facilit 0 eratin License DPR-67 On March 18,,1977, Florida Power and Light Company (FPL)submitted its proposed pump and valve test program for St.Lucie Unit No.1.Proposed Technical Specification changes to conform the Technical Specifications to the'evised program were also-submitted as required by 10 CFR 50.55a (g)(5)(ii).Your letter of May 24, 1977, acknowledged receipt of these items and requested additional information for the purpose of evaluating, ou'r proposed program'.The information which you requested is contained in"Attachment A to this letter.".As a result of the review which has been prompted by your request for additional information and discussions faith your"'Staff, FPL has made numerous changes in the proposed pump and valve test program for the purpose of providing additional clarification.

Although we be-.lieve that none of these changes are of a substantive nature, we are nonetheless submitting a revised program to replace in toto that which was forwarded to you on March 18.The revised program is contained in Attachment.

B to this letter and is identified by the date 9/16/77 on'each page.Exceptions to the ASME Code,Section XI requirements are identified and supporting information is presented in"Table II of the revised proposed program in accordance with the provisions of 10 CFR 50.55a(g)(5)(iii).

Relief from those require-ments's herewith requested.

As per instructions from members of your Staff, FPL is also forward-ing under separate cover ten sets of the drawings used in the develop-ment of the revised proposed pump and valve test.program.One of these sets has been marked-up to show the various system boundaries.

Our submittal of March 18 included proposed Technical Specification changes to conform the Technical Specifications to the requirements of the proposed test program.As a result of our review of the program, we find it necessary to withdraw some of the proposed q g g 7 7@2 s3.PEOPLE...SERVING P EOP LE 0'Oflice of Nuclear Reactor Regulation Attn: Mr.Victor Stello Page 2 Technical Specification changes submitted at that.time either aa being unnecessary or for the purpose of further modification.

Please delete the following items from our March 18 submittal:

S ecification Pa e 1.21 4.0.5 4.7.1.2.b 3/4.0.5 3/4.6.1.2 3/4/7.1.1 1-5 3/4 0-2 3/4 7-5 B3/4 0-3 B3/4 6-1 B3/4 7-1 Xn accordance with instructions'ontained in your letter of January 14, 1977 to FPL regarding exemption from the initial imple-mentation requirements of 10 CFR 50.55a.(g), a proposed in-service inspection program for St.Lucie Unit No.1 for ASME Code Class 1,2 and 3 components, together with appropriate proposed Technical Specification changes, were submitted to you on July 1, 1977.As a result of additional modifications required to the items proposed, which are described below, we request that the following items from our July 1 submittal be deleted: S eciXication Pa e 4.0.5 3/4 0-'2 3/4.0.5 B3/4 0-3 Additional Technical Specification changes have been identified pursuant to our review of the entire in-service testing and inspection program.Pursuant to the'requirements of 10 CFR 50.55a(g)(4)(ii) and in accord-ance with 10 CFR 50.30, FPL herewith submits three signed originals and forty (40)copies of a supplemental request.to amend Appendix A of Facility Operating License DPR-67.The additional proposed Technical Specification changes are described below and shown on the accompanying Technical Specification pages in Attachment C bear-ing the date of this letter in the lower right hand corner.The following Specifications are deleted, added or revised to conform the existing" Technical Specifications to the revised proposed pump and valve'test and in-service*inspection program.Remarks 4.0.5 (Added)4.4.2~(Revised)3/4 0-2@3 3/4 4-2 New Specification 4.0.5 is added to specify the pump and valve test re-.quirements.

Reactor Coolant System-Safety Valves (Shutdown):

pressurizer code safety valve tests referenced to Specification 4.0.5.

1 h Office of Nuclear Reactor Regulation Attn: Mr.Victor Stello Page 3 S ecification 3.4.10.1 (Deleted)Pa e 3/4 4-26 Remarks Reactor Coolant System-Structural Integrity (Safety Class 1 Components):

LCO superseded by proposed Specifica-tion 3.4.10.1 below.4.4.10.1 (Deleted)Table 4.4-6 (Deleted)34 4-26a27 3/4 4-28 to 36 Reactor Coolant System Structural Integrity (Safety Class 1 Components):

Surveillance superseded by proposed Specification 4.4.10.1 below.In-service Inspection Program-Safety Class 1 Components:

Superseded by proposed Specification 4.4.10.1 below.3.4.10.2, (Deleted)4.4.10.2 (Deleted)3/4 4-37'/4 4-37 a 38: Reactor Coolant System-Safety Class 2 Components:

LCO superseded by propose'd Specification 3.4.10.1 below.Reactor Coolant.System-Safety Class 2 Components:

Surveillance.superseded by proposed, Specification 4.4.10.1 below.Table 4.4-7 (Deleted)3/4 4-39 to 52 In-.,service Inspection Program-Safety Class 2 Components:

Superseded by pro-posed Specification 4.4.10.1 below.3.4.10.3 (Deleted)3/4 4-53 Reactor Coolant, System-Safety Class 3 Components:

LCO superseded by proposed Specification 3.4.10.1 below.4.4.10.3 (Deleted)Table 4.4-8 (Deleted)3.4.10.1 (Added)4.4.10.1 (Added)3/4 4-53 a 54 3/4'-55 3/4 4-26 3/4 4-26 Reactor Coolant: System-Safety Class 3 Components:

Surveillance superseded by proposed Specification 4.4.10.1 below.In-service Inspection Program-Safety Class 3 Components:

Superseded by pro-posed Specification 4.4.10.1 below.Reactor Coolant, System-3.4.10 Structural Integrity (ASME Code Class 1, 2 and 3 Components):

LCO's for ASME Code Class 1, 2, and 3 Components referenced to ASME Code requirements.

Reactor Coolant System-3.4.10 Structural Integrity (ASME Code Class 1, 2 and 3 Components):

Surveillances referenced to Specification

4.0.5. Office

of Nuclear Reactor Regulation Attn: Mr.Victor Stello Page 4 Specification Pa e Remarks 4.5.2.f (Added)4.6.2.l.d (Added)3.6.3.1 (Revised)3/4 5-6 3/4 6-16 3/4 6-18 Emergency Core Cooling Systems-ECCS Subsystems (T>300 F): ECCS sub-system valve NSts referenced to Specification 4.0.S.Depressurization and Cooling Systems-Containment Spray System: Containment spray system pump and valve tests referenced to Specification 4.0.5.Containment Systems-Containment, Isola-tion Valves: Clarification of test times in Table 3.6-2 is provided.4.6.3.1.3 (Added)4.7.1.2.b (Revised)4.7.3.1.c (Added)4.7.4.l.c (Added)3/4 6-19 3/4 7-5, 3/4 7-15 3/4 7-17 Containment Systems-Containment Isola-tion Valves: Isolation valve tests ref-erenced to Specification 4.0.5.3 Plant Systems-Auxiliary Feedwater System: Feedwater pump and valve tests referenced to Specification 4.0.5.Plant Systems-Component Cooling Water System: CCW pump and valve tests referenced to Specification 4.0.S.Plant Systems-Intake Cooling Water System: ICW pump and valve tests referenced to Specification 4.0.5.-3/4.0.5 (Added)3/4.4.10 (Revised)B3/4 0-3 B3/4 4-12 a 13 A new Bases section is added to corres-pond to new Specification 4.0.5.The Bases section on Structural Integrity is revised to incorporate reference to surveillance performed in accordance with the applicable ASME Code and Addenda.The FRG and CNRB have reviewed these proposed Technical Specification changes and have concluded that they do not involve an unreviewed safety question.Very yours,~~Ro r E.Uhrig Vice President REU/LLL:ltm Attachments cc: Robert Lowenstein, Esq.J.P.O'Reilly, Region II 0\

STATE OF FLORIDA))CO~I.TY OF DADE)ss E.A.Adomat being first.duly sworn, deposes and says: That he is Executive Vice President Light Company, the Licensee herein;of Florida Power&That he has executed the foregoing document.;

that the state-ments made in this said 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..A.Adomat Subscribed and sworn to before me this day of 19 y7ÃOTARY PUBLIC, xn and for the County of Dade, State of Florida hO?AITY PUOUO S7A76 OF TLOIIIDA tt VIIGG py commission expires-o

'j ly N il I., l