ML20214V639

From kanterella
Jump to navigation Jump to search

Amend 140 to License DPR-57,modifying Tech Spec Table 3.7-4 to Delete Certain Valves Listed as Containment Isolation Valves Requiring Leak Tests & Changing Pressure at Which MSIVs Required to Be Tested
ML20214V639
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 06/05/1987
From: Youngblood B
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20214V641 List:
References
TAC-64785, NUDOCS 8706120212
Download: ML20214V639 (9)


Text

-

i UNITED STATES

[

p, NUCLEAR REGULATORY COMMISSION 5

'j WASHINGTON, D. C. 20555

%...../

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No.140 License No. DPR-57 1.

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

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Georgia Power Company, acting for itself, Oglethorpe-Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) date<1 March 4,1987, and supplemented April 21, 1987, 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 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 2

in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the i

public; and i

E.

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

t been satisfied.

I g6120212870605 7

p ADOCK 05000321 PDR

.~

, 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and-paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

(2)

Technical Specifications

.The Technical Specifications contained in Appendices A and B, as revised through Amendment No.140, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION 6\\

B. J. Youngblood, Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Changes to the Technical Specifications Date of Issuance: J une 5, 1987 T

MDdII-h/DRP-I/II PD#II-3/DRP-I/II PD#

OGC ethesda PD#I!-3/DRP-I/II rlhan 4>%*h BJYoungblood LCrocker/mac 05/n /87 05/g/87 05

/87 05/g/87 N

I

. ~,

... ~. - -, - -

ATTACHMENT TO LICENSE AMENDMENT N0.140 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET N0. 50-321 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 areas of change.

Remove Insert Page Page 3.7-6a 3.7-6a 3.7-24 3.7-24 3.7-25 3.7-25 3.7-26 3.7-26 3.7-26a 3.7-26a 3.7-26b 3.7-26b

LIMillNG COND1110NS FOR OPERATION SURVEILLANCE REQUIREMENTS g.

Acceptance Criteria for Tvoe B and Type C Tests The combined leakage rate of components subject to Type B and C tests shall be determined under the program established in Appendix J of 10 CFR Part 50 and shall not exceed 0.6 L -

a h.

Main Steam Line Isolation Valves The main steam line isola-tion valves shall be tested at a pressure of 28 psig for leakage at least once per operating cycle.

If a total leak rate of 11.5 scf per hour for any one main steam line isolation valve is exceeded, repairs and retest shall be performed to correct this condition.

HATCH -.411 1 3.7-6a Amendment No. 140

Table 3.7-4 (Continued)

Primary Containment Testable Isolation Valves Penetration Number Valve Designation

' Notes X-18 G11-F019 & F020 (1) (2) (4) (5) (9)

X-19 G11-F003 & F004 (1) (2) (4) (5) (9)

X-20 P41-F049 (1) (2) (4) (5) (9)

X-21 P51-F513 & F514 (1) (2) (4) (5) (9)

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

X-23 P42-F051 (1) (2) (4) (5) (10)

X-24 P42-F052 (1) (2) (4) (5) (10)

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

X-25 T48-F113 (1) (2) (4) (5) (14)

X-25 T48-F321 (1) (2) (4) (5) (14)

X-25 T48-F104 (1) (2) (4) (5) (14)

X-25 T48-F114, F118A & F322 (1) (2) (4)-(5) (10).

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

X-26 T48-F334A (1) (2) (4) (5) (14)

X-26 T48-F3348 (1) (2) (4)-(5) (14)

X-26 T48-F335A & F335B (1) (2) (4) (5) (10)

X-26 T48-F340 & F341 (1) (2) (4)-(5) (9)

X-26 P33-F002 (1) (2) (4) (5) (10)

X-26 P33-F010 (1) (2) (4) (5) (14)

X-27A 011-F051 & F053 (1) (2) (4)-(5) (10)

X-27F P70-F066 & F067 (1) (2) (4) (5) (10)

HATCH - UNIT 1 3.7-24 Amendment No. 140

.m.

Table 3.7-4 i

(Continued)

Primary Containment Testable Isolation Valves Penetration Number Valve Designation Notes X-28F P33-F003 & F011 (1) (2) (4) (5) (9)

X-28A B31-F019 & F020 (1) (2) (4) (5) (9)

X-310 P33-F004 & F012 (1) (2) (4) (5) (9)

X-31F B31-F013A & F017A (1) (2) (4) (5) (10)

X-33C D11-F050 & F052 (1) (2) (4) (5) (10)

X-34E P33-F005 & F013 (1) (2) (4) (5) (9)

X-35A C51-Ball Valve (1) (2) (4) (5) (10)

X-358 C51-Ball Valve (1) (2) (4) (5) (10)

X-35C CSI-Ball Valve (1) (2) (4) (5) (10)

X-350 CSI-Ball Valve (1) (2) (4) (5) (10)

X-35E CSI-Nitrogen Inerting Check Valve (1) (2) (4) (5) (10)

X-39A E11-F016 A (1) (2) (4) (5) (9)

X-39B E11-F016B (1) (2) (4) (5) (9)

X-40C P70-F002 & F003 (1) (2) (4) (5) (9)

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

X-42 C41-F007 (1) (2) (4) (5) (10)

X-44 P41-F050 (1) (2) (4) (5) (9)

X-45F T23-F004 & F005 (1) (2) (4) (5) (9)

X-46 P21-F353 & F420 (1) (2) (4) (5) (9)

X-528 B21-F111 & F112 (1) (2) (4) (5) (10) (11)

X-59A B31-F013B & F0178 (1) (2) (4) (5) (10) l

'\\il

- UNIT 1 3.7-25 Amendment No. 140

Table 3.7-4 (Continued)

Prim ry Containment Testable Isolation Yalves Penetration Number Valve Designation Notes X-205 T48-F310 & F328A (1) (2) (4) (5) (9)

X-205 T48-F115 & F116 (1) (2) (4) (5) (9)

X-205 T48-F311 &'F3288 (1) (2) (4) (5) (9)

X-205 T48-Fil88 (1) (2) (4) (5) (10)

X-205 T48-F325 & F327 (1) (2) (4) (5) (9)

X-250 T48-F104 (1) (2) (4) (5) (14)

X-206A E41-F121 & F122 (1) (2) (4) (5) (9)

X-211A E11-F027A & F028A (1) (2) (4) (5) (9)

HATCH - US T 1 3.7-26 Amend:nent No.140

Table 3.7-4 i

(Continued)

Primary Containment Testable Isolation Valves Penetration Number Valve Desionation Notes X-211B E11-F027B & E11-F028B (1) (2) (4) (5) (9)

X-212 E51-F001 & F040 (1) (2) (4) (5) (9)

X-213 E51-F002 & F028 (1) (2) (4) (5) (g)

X-214 E41-F021 & F049 (1) (2) (4) (5) (9)

X-215 E41-F022 & F040 (1) (2) (4) (5) (9)

X-217 P33-F007 & F015 (1) (2) (4) (5) (9) i HATCH - UNIT 1 3.7-26a Amendment No. 140 l

l l

Table 3.7-4 (Continued)

Primary Containment Testable Isolation Valves Penetration Number Valve Designation Notes l

'X-220 P33-F006 (1) (2) (4) (5) (14)

X-220 P33-F014 (1) (2) (4) (5) (10)

X-220 T48-F318 & F326 (1) (2) (4) (5) (9)

X-220 T48-F332A (1) (2) (4) (5) (14)

X-220 T48-F332B (1) (2) (4) (5) (14)

X-220 T48-F333A & F333B (1) (2) (4) (5) (10)

X-220 T48-F338 & F339 (1) (2) (4) (5) (9)

X-221r E51-F104 & F105 (1) (2) (4) (5) (9)

X-222A E41-F111 & F104 (1) (2) (4) (5) (9)

X-223A T48-Air Cylinder (1) (2) (4) (5) (11)

X-223A T48-F342G-L (1) (2) (4) (5) (11)

X-223B T48-Air Cylinder (1) (2) (4) (5) (11)

X-223B T489-F342A-F (1) (2) (4) (5) (11) l-i,.

1 l

-i i

l HATCH - UNIT 1 3.7-26L Amendment No. 140 j

_.