ML20133G440

Amend 72 to License DPR-54,revising Tech Specs to Change Closure Times of Several Containment Isolation Valves in Table 3.6-1 & Require Leak Rate Testing of Equipment Hatch & Fuel Transfer Tube Seals After Each Opening

ML20133G440
Person / Time
Site:	Rancho Seco
Issue date:	07/30/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133G408	List: ML20133G406 ML20133G440 ML20133G468
References
TAC-55532, NUDOCS 8508080681
Download: ML20133G440 (5)

Text

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UNITED STATES t

NUCLEAR REGULATORY COMMISSION h.

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WASHINGTON D. C. 20555 e

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-54 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Sa'cramento Municipal Utility District (the licensee) dated June 20, 1984, as revised by. letter of February 25, 1985, complies with the standards and requirements of the Atomic Er. orgy Act of 1954 as amended (the Act), and the Comission's rules and regula*. ions set forth in 10 CFR Chapter I; B.

The facil.ity will operate in conformity with the application, the the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, andparagraph2.C.(2)ofFacilityOperatingLicenseNo.DPR-54ishereby amended to read as follows:

85080806R1 850730 PDR ADOCK 0S000312 P

PDR

s 2-l Technical Specifications i

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

1 FOR THE NUCLEAR REGULATORY COMMISSION JaTh F. Stolz, Chief p'h #4 0 rating Reactors BrAnc ivision of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: " July 30,1985 G

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ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. OPR-54 DOCKET NO. 50-312 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

't Remove Insert 3-40 3-40 4-18 4-18 i

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RANCHO SECO UNTT 1 TECHNfCAL SPECIFICATIONS Limiting Conditions for Operation I

Tab'le 3.6-1 l

SAFETY FEATURES CONTAINMENT ISOLATION VALVES VALVE NtMBER DESCRIPTION MAXIMUM CLOSURE TIME (SEC)

SFV 53612 R8 Atm. Purge Sampl e, AB ST de. h....................... 3 SFV 53613 R8 Atm. Aad Sample AB Side.......................... 3 SFV 60003 RC Sy s. D rai n I sol. AB Si de........................... 14 j

SFY 66308 R8 Normal Sump Drai n, A8 Si de......................... 15

(

SFV 92520 Przr. Ni trogen Isol., AB Si de......................... 3 l

SFV 53503 R8 P urge Inl et, A8 Si de............................... 5 SFV 53604 R8 P u rge Outl e t, AB S 16e.............................. 3 SFV 53610 R8 Pre s s. Equal izer, AB Si de.......................... 15

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SFV 60002 RC System Vent Isol., AB Side.........................

8 l

~

i SFV 60004 RC System Drain Isol., AB Side........................

14 1

SFY 66309 R8 Normal Sump Drai n, A8 Si de......................... 11 j

s SFV 70002 Prz r. Li qui d Sampl e Isol. A8 Si de.................... 8 SFV 72502 Prz r. Ga s Sampl e Isol., A8 Si de....................... 6 l

l HV 20611 GTSG's Blowdown Isol., AB Side........................

22 l

HV 20593 OTSG-A Sampl e Isol., AB Si de.......................... 12 HV 20594 OTSG-8 Sample Isol., AB Side..........................

5 SFV 53504 R8 P urge Inl et, R8 Si de....S.......................... 5

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i SFY 53603 R8 P re s s. Equal i zer, R8 Si de.......................... 9 j

SFY 53605 R8 P u rge Outl et, R8 Si de.............................. 5 l

SFV 60001 RC Sy s. Ve nt I sol, R8 Si de............................ 12 l

SFY 70001 Przr., Li oui d Sampl e I sol., RB Si de.................... 21 l.

SFV 70003 Przr. Vapor Sampl e Isol., R8 Side..................... 21 4

1 SFY 72501 Przr. Ga s Sampl e I sol., R8 51 de....................... 9

• SFY 46014 R8 CCW Sup ply AB Si de................................ 14 '

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• SFY 46203 RS CCW Re turn, R8 Si de................................ 14 l

• SFV 46204 R8 CCW Return, AB Si de................................ 18 l

• SFV 46906 CRD Cool i ng Water Sup ply, AB Si de..................... 13 l

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• SFV 46907 CR0 Cool i ng Water Return, R8 Si de..................... 14 j

• SFY 46908 CRD Cool i ng Water Return A8 Si de..................... 11 l

l 1

• HV 20609 OTSG-A Blowdown Isol., R8 Side........................

15 i

• HV 20610 0TSG-8 Bl owdown I sol., R8 Si de........................ 14 j

SFY 22023 RC Sy s. Letdown, R8 Si de.............................. 15 l

l SFY 22009 RC Sy s. Letdown, A8 51 de.............................. 7 l

l SFV 24004 RC Pump Seal Return, R8 Si de.......................... 71 SFV 24013 RC Pump Seal Return, AS Si de.......................... 12 l

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• Manual initiation signal (no auto. initiation)

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t Amendment No. U,72 3-40 t

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i RAEHO SECO UNII 1 TECHNICAL SPECIFICATIONS i

Surveillance Standarus (20)

Pressurizer relief tank nitrogen supply line (21)

Pressurizer sar.iple line (22)

Reactor coolant drain tank header (23)

Reactor Building hyorogen sample line (24)

H2 recomoiner penetration 4.4.1.2.2' Conduct of Tests i

(a) With the exception of the personnel and emergency hatches coor seals, all local leak rate tests shall ne performed at a pressure of riot.less tnan 52 psig. See Paragrapn i

4.4.1.2.Sc for personnel and emergency haten coor seal test pressure.

l (D) Acceptaole methods of testing are halogen gas antection, soap bubbles, pressure decay, hydrostatic _ flow or

., equivalent.

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4.4.1.2.3 Acceptance Criteria 1

i The total leakage from all penetrations anc isolation valves l

sh411 not exceed 0.06 percent of the Reactor Building atmospnere per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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4.4.1.2.4 Corrective Action and Retest f

(a) If at any time it is aetermined that tne criterion of 4.4.1.2.3 above is exceeded, repairs shall be initiated l

immediately, i

I (o) If conformance to the criterion of 4.4.1.2.3 is.not demonstrated within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> following detection of 1

excessive local leakage, the reactor shall De shut cown i

and depressurized until repairs are effected and the local leakage meets the acceptance criterion as demonstrated by retest.

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4.4.1.2.5 Test Frequency Local leak detection tests shall be performee at a frequency of at least each refueling interval, except that:

t (a) The equipment hatch and fuel transfer tube seals snall be I

additionally tested af ter each opening. This testing shall i

be done prior to containment integrity being reqvfree ey Specification 3.6.1.

(o) The personnel and emergency hatches shall be tested between the inner and outer coors at a pressure not less than 52 psig semi-annually.

4-18 knendments Nos.11. #,72

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