ML20141F121

Amends 120 & 59 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Add & Delete Values Listed in Containment Isolation Value Tables to Reflect Drywell Pneumatic Sys Mods

ML20141F121
Person / Time
Site:	Hatch
Issue date:	12/26/1985
From:	Muller D Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141F117	List: ML20141F112 ML20141F121 ML20141F126
References
TAC-59558, TAC-59559, TAC-59588, TAC-59589, NUDOCS 8601080629
Download: ML20141F121 (10)

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UNITED STATES

- E o NUCLEAR REGULATORY COMMISSION s :y WASHWGJOP!, D. C. 20565 s.,...../

GEORGIA PDWER COMPANY

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OGLETHORPE'F0WER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DkTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.120 License No. DPR-57

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

A. The application for amendment by Georr;ia Power Company, et 'al.,

(the licensee) dated August 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; s i, ..

C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted withoJt endangering tiie 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 common defense and security or to the health and safety of the public; and s E. The issuance of this' amendment is[in a::cordance 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,

+' and psragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

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i 8601080629 B51226 DR ADOCK O y1

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2-Technical Specifications

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'f 41 The Technical Specifications contained in Appendices M- A and B, as revised through Amendment No.120, are

+ hereby incorporated in the license. The licensee shall operate the facility in accordance with the 4 ,

Technical Specifications.

p1: s' 3.- This license amendment is effective as of its date of issuance and shall i be implemented within 30 days of issuance.

>! OR THE NUCLEAR REGULATORY C0ml ION I,

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s Daniel R. Muller, Director BWR Project Directorate #2 V Division of BWR Licensing

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.m i[{ttachment:

(Lianges to the Technical Specifications

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Date of Issuance: December 26, 1985

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i ATTACHMENT TO LICENSE AMENDMENT NO. 120 j FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

Remove Insert 3.7-24 3.7-24 f

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Table 3.7-4 (Continued)

Primary Containment Testable Isolation Valves Penetration Number Valve Designation Notes X-21 P51-F513 & F514 (1) (2) (4) (5) (9)

X-22 P70-F004, F005 (1) (2) (4) (5) (10)

X-25 T48-F307, F308, F309, F103 & F324 (1) (2) (4) (5) (9)

X-25 T48-F113 & F114 (1) (2) (4) (5) (9)

X-25 T48-F321 & F322 X-25 T48-F104, F118A, F1188 (1) (2) (4) (5) (9)

X-26 T48-F319 & F320 (1) (2) (4) (5) (9)

X-26 T48-F334A & F335A X-26 T48-F334B & F335B X-26 T48-F340 & F341 X-26 P33-F002 & F010 X-27F P70-F066, F067 (1) (2) (4) (5) (10)

X-28 P33-F003 & F011 (1) (2) (4) (5) (9)

X-31 P33-F004 & F012 "

X-36 C11-F086 (1) (2) (4) (5) (10)

X-36 C11-F083 X-39A E11-F016A & F021A (1) (2) (4) (5) (9)

.X-39A E11-F016B & F0218

+ X-40 P70-F002 & F003 X-41 B21-F019 & F020

} X-42 C41-F006 (1) (2) (4) (5) (10)

X-42 C41-F007 X-46 P21-F353 & F406 (1) (2) (4) (5) (9)

X-203 E-51-F003 & F031

. X-204A E11.F065A'& F004A (1) (2) (5) (9) (12)

Amendment No. 57,120 3.7-24

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%,*****e' GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPALEldCTRICAUTHORITYOFGEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-5

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Georgia Power Company, et'a1.,

(the licensee) dated August 23, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) 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 Commission's regulations; D. The issuance of this amendment will not be inimical to the common 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 31 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in tae attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59 , 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 and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

$ 44 /

Daniel R. Muller, Director BWR Project Directorate #2 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 26, 1985

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ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert 3/4 6-24 3/4 6-24 3/4 6-25 3/4 6-25 3/4 6-26 3/4 6-26 3/4 6-27 3/4 6-27 * -

3/4 6-28 3/4 6-28 i

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31 TABLE 3.6.3-1 (Continued) I g PRIMARY CONTAIMENT ISOLATION VALVES

-e E ISOLATION TIME i VALVE FUNCTION AND NUMBER VALVE GROUP (a) (Seconds)  ;

b A. Automatic Isolation Valves (Continued)

' 25. Traversing Incore Probe Isolation Valve .s; Ball Valves

• NA s'f -

26. Vacuum Relief Isolation Valves 2T48-F309 6 5 2T48-F324 6 5 g "I See Specification 3.3.2. Table 3.3.2-1, for isolation signals that operate each valve group. i

[ Closes upon withdrawal of TIP. TIP automatic withdrawal is actuated by either low reactor -

vessel water level or high drywell pressure.

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4 TABIE 3.6.3-1(Oontirued)

• M PRDERY CDtfrAIMElfr ISO [ATION VALVES

~I i VALVE RJNCTION AND ID EER B. t!At0AL ISOIATION VALVES (e) l g .

1. Main steam isolation valves 2E32-F001B, F, K, P

2. IER return to recirottlation loop isolation valtes l 2 Ell-F015A, B i 3. LOCA H2 recombiner isolation valtes 2T49-F002 A, B 2r49-F004 A, B y 4. Chre spray isolation valves

• - 2221-F005A, B i

, y 5. Service air isolation valtes 2P51-F651 2P51-F513 j I i

y 6. RBOCW sJpply and return isolation valtes

, g 2P42-F051

? 2P42-F052 ,

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'*) Includes power operated valves which do not isolate aitomatically.

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< t I. TABLE 3.6.3-1 (Continued) j

' PRIMARY CONTAINMENT ISOLATION VALVES iE i

@ VALVE FUNCTION AND NUMBER e B. I

• MANUAL ISOLATION VALVES ') (Continued)

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" Drywell pressure instrumentation line isolation valves 2E11-F041A, B, C, D l 2T48-F363A, B 8.

-! ILRT verification flow isolation valves 2T23-F004 '

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I 2T23-F005 j 9. Traversing incore probe isolation valve Shear valve (explosive) [

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' " 10. N2 makeup inlet isolation valves

• 2T48-F321 .l l

/ 2T48-F322 1.

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? 2T48-F325 C

IX 2T48-F327 1

11. Demineralized water isolation valves

[' 2P21-F032 ,

l 4i 2P21-F034 17 12. Chilled water supply and return isolation valves Y 2P64-F045 j

, a 2P64-F047

.i g 13. Chemical pump discharge isolation valves 2G11-F852 E 2G11-F853 l li E i >

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PRIMARY CONTAINMENT ISOLATION VALVES VALVE FUNCTION AND NUMBER

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E B. MANUAL ISOLATION VALVES (e) (Continued) 1 0 c- 14- Nitrogen vent isolation valves i'i l

• 2T48-F332 A, B 2T48-F333 A, B 2T48-F334 A, B 2T48-F335 A, B 15 Nitrogen inlet isolation valves I 2T48-Fil3 2T48-F114

16. RCIC pump suction isolation valves l 2E51-F003 2E51-F031 17- RHR pump suction isolation valves j g 2 Ell-F004A, B, C, D IS. Vacuum relief isolation valves l-

? 2T48-F310 9? 2T48-F311 19' Vacuum relief instrumentation line isolation valve 2T48-F364A, B l

20. Torus water l'e' vel instrumentation line isolation valves j-2T48-361 A, B 2T48-362 A, B

[ 21* HPCI pump suction isolation valve {

g 2E41-F051 5 22. Core spray pump suction isolation valves A 2E21-F001 A, B l I

23. Fire protection isolation valve 2T43-F160 l y- '

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TABLE 3.6.3-1 (Continued) lE PRIMARY CONTAINMENT ISOLATION VALVES M

x VALVE FUNCTION AND NUMBER

!! B. MANUAL ISOLATION VALVES I *I (Continued) h3 1' 24. FPM sample isolation valves I

2D11-F058 i 2011-F061

- , 25. Torus purification suction isolation valves l I- 2G51-F002 26't RHR relief valve discharge isolation valve

] 2E11-F103 A, B l I' ~

as 27. Nitrogen makeup isolation valves -(

3: 2T48-F115 2T48-F116 ai '

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[ 28. Core spray test line isolation valves [

,' 2E11-F007 A, B I .

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' mbt 2 3.6.3-1 (Contimed)

• PRDERY CONTADMENP ISCIATION VALVES

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C. ODIER ISOUn' ION VALVES

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M 1. Primary feedwater isolation valtes 2B21-F010 A, B 2B21-F077 A,(f) B(f)

2. Drywell pneumatic return isolation valves 2P70-F004

• 2P70-F005 2P70-F066 2P70-F067

3. Recirculation line flow instmmentation line isolation valtes(9) w 2B31-F009 A, B, C, D 1 2B31-F010 A, B, C, D 2B31-F011 A, B, C, D 7

y 2B31-F012 A, B, C, D

4. Reciraalation pump seal pirge isolation valtes 2B31-F013 A, B 2B31-F017 A, B

5. Pecirculation line pressure instmmentation line isolation traltes(9) 2931-F057 A, B

6. Recirculation pure discharge pressure instmmentation line isolation va15es(9) 2B31-F040 A, D ,

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Po (f) Air assist check valte

", (9) Excess flow check valte E I i

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