Text

Amends 27 & 8 to Licenses NPF-68 & NPF-81,respectively. Amends Revise Requirements for Inoperable Containment Hydrogen Monitors for Consistency
	ML20012B397
Person / Time
Site:	Vogtle
Issue date:	02/20/1990
From:	Matthews D; Office of Nuclear Reactor Regulation
To:	; Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20012B398	List: ML20012B397; ML20012B402;
References
	NPF-68-A-027, NPF-81-A-008 NUDOCS 9003140336
	Download: ML20012B397 (9)
	v • d • e

.6

=

o..

' l('peusy(

i UNITEG)SYA NS l

NUCLEAR REGULATORY COMMISSION n

E WASHINGT0h'. D. C. 70f46 t

GEORGIA POWER COMPAfiY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA l

CITY OF DALTON. GEORGIA V0GTLE ELECTRIC GENERATING PLANT, llNIT 1 AMENDMENT TO FACILITY OPEP.ATING LICENSE l

Amendment No. 27 License No. NPF-68 j

1.

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

l The app (lication for amendment to the Vogtle Electric Generating Plant, A.

Unit 1 the facility) Facility Operating License No. NPF-68 filed by the Georgia Power Company acting for itself, Oglethorpe Power Corpo-ration, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensees) dated November 7}es with the standards and 1988, and supplenented December 1,1980, and May 19, 1989 coup 1 requirenents of the Atomic Energy Act of 1954, as amended (the Act),

i end the Commission's rules and regulations set forth in 10 CFP Chapter It i

B.

The facility will operate in conformity with the application, as anended, the provisions of the Act, and the rules and regulations of the Com.ission; r

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

The issuance of this license amendment will r.ot be inimical to the 1

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 Consaission's regulations and all applicable requirements have been satisfied.

9003140136 900220 PDR ADDCK 05000424 E

PDC

E 1 7;-

i i

2 l

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-68 is hereby i

amended to read as follows:

t Technical Specifications and Environmental Protection Plan i

The Technical Specifications contained in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are i

hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall l

be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION i

/2)

Da d B. Matthews, Director Project Directorate 11-3 Division of Reactor Projects - I/I!

Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance: February 20, 1990 I

f I

g

esmeeg 7

UNITO STATES l,

NUCLEAR RECULATORY COMMISSION a

'5 WASHINGTON, D, C. POME

\\....**/

i j

GEORGIA POWER COMPANY I

OGLETHORPE POWER CORPORATION j

FUNICIPAL ELECTRIC AUTHORITY OF GEORGIA I

CITY OF DALTON. GEORGIA l

V0GTLE ELECTRIC GENERATING PLANT UNIT 2 j

AMENDMENT TO FACILITY OPERATING LICENSE t

Amendment No. 8 f

License No. NPF-61 l

1.

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

The app (lication for amendment to the Yogtle Electric Generating Plant, A.

Unit 2 the f acility) Facility Operating License No. NPF-01 filed by the Georgia Power Company acting for itself Oglethorpe Power Corpo-i ration, Municipal Electric Authority of Georgia, and City of Daltcn, l

Georgia, (the licensees) dated November 7,1988, and supplemented December 1,1988, and May 19, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amerded (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, as amended, the provisions of the Act, and the rules and regulations of the Comission; C.

Thereisreasonableassurance(1)thattheactivitiesauthorizedby this emendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this license 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 requirenents have been satisfied.

4 0

I

O l: '

2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendnent and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 8. and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. GPC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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 COPtilSSION JA l

David B.

tthews, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation I

p

Attachment:

i Technical Specification Changes l

i Date of issuance: February 20, 1990 l

1

'o i

i i

ATTACHMENT TO LICENSE AMENDMENT NO.27 FACILITY OPERATING LICENSE NO. NPF-68

)

AND LICENSE AMENDMENT NO. 8 i

FACILITY OPERATING LICENSE NO. NPF-81 DOCKETS NOS. 50-424 A2 50-425 Replace the following pages of the Appendix "A" Technical Specifications with I

the enclosed pages.

The revised pages art identified by Amendment number and contain vertical lines indicating the areas of change.

Amer.ded Page 3/4 3-59 3/4 3-60 3/4 3-61 3/4 3-62 V

b 9

h

m TABLE 3.3-8

-l S

ACCIDENT MONITORING INSTRUMENTATION E

c-TOTAL MINIMUM 5

NO. OF CHANNELS d

INSTRUNENT CHANNELS OPERABLE ACTION b

1.

Reactor Coolant Pressure (Wide Range) 4 1

35 (Loop 408, 418, 428. & 438) e.

2.

Reactor Coolant System Thot (Wide Range) 1/ loop 1/ loop

' 32 L

(Loop 413A, 423A, 433A & 443A) 3.

Reactor Coolant System Tcold (

Range) 1/ loop M oop 32 (Loop 4138, 4238, 433B & 443B)

R 4.

SG Water Level (Wide Range) 1/SG 1/SG 32 (Loop 501, 502, 503 & 504)

?'$

5.

SG Water Level (Narrow Range) 4/SG 1/SG 35 (Loop 517, 518, 519, 527, 528, 529, 537, 538, 539, 547, 548, 549, 551, 552, 553, 554) 6.

Pressurizer Level 3

1 30 (Loop 459, 460, 461) gg 7.

Containment Pressure 4

1 35 gg (Loop 934, 935, 936, 937)

EE gg 8.

Steamline Pressure 3/sta. line 1/stm. line 30 (Loop 514, 515, 516. 524, 525, 526, 534, 535, 536, 544, gg 545 & 546)

O 9.

RWST Level 4

1 35 gg (Loop 990, 991, 992 & 993) zz UU 10.

Containment Normal Sumps Level (Narrow Range) 2 1

31a l

Og (Loop 7777 & 7789) 11.

Containment Water Level (Wide Range) 2 1

31a l

(Loop 0764 & 0765)

O

.n TABLE 3.3-8 (Continued)

~~

8 g

ACCIDERi MONITORING INSTRUMENTATION g

TOTAL MINIMUM NO. OF CHANNELS U

INSTRUMENT CHANNELS OPERAELE ACTION 12.

Condensate Storage Tank Level 2/ tank 1/ tank-31a l

(Loop 5101, 5111, 5?04 & 5116) c.

~

13. Auxiliary Feedwater Flow 2/ feed line 1/ feed line

' 31a j

(Loop 5152, 15152, 5153, 15153, 5351, 15151, 5150 & 15150) 14.

Containment Radiation Level (High k nge) 2 1

33 (Loop 0005 & 0006) 15.

Steamline Radiation Monitor 1/stm. line 1/sts. line 33 y

(Loop 13119, 13120, 13121 & 13122) 16.

Core Exit Thermocouples 4/ quad / train 2/ quad / train 30 17.

Reactor Coolant System Subcooling 2

1 31a l

18.

Neutron Flux (Extended Range) 2 1

31a l

(Loop 13135A & 131358) 19.

RVLIS 2

1 34 EE EG

20. Containment Hydrogen Concentration 2

1 31b l.

EE (Loop 12979 & 12980) zz[

21.

Containment Pressure (Extended Range) 2 1

31a l

pp (Loop 10942 & 10943)

22. Containment Isolation Valve Position Indication

1/ valve 1/ valve 36 EE "Applicabie for containment isolation valve position indication designated as post-accident monitoring instru-30 mentation (containment isolation valves which receive containment isolation Phase A or containment ventilation isolation signals).

TABLE 3.3-8 (Continued)

ACTION STATEMENTS 4

ACTION 30

- a.

With the number of OPERABLE channels one less than the Total I

Number of Channels requirement, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With the number of OPERABLE channels two less than the Total Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days, or be in at least HOT i

SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

With the number of OPERABLE channels less than the Minimum 5

Channels OPERABLE requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , d.

The provisions of Specification 3.0.4 are not applicable.

t ACTION 31a - a.

With the number of OPERABLE channels one less than the Total

[

Number of Channels requirement, restore one inoperable channel s

to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c.

The provisions of Specification 3.0.4 are not applicable.

ACTION 31b - a.

With the number of OPERAPLE channels less than the Total f

Number of Channels rquirement, coneply with the provisions of Specification 3.6.4.1.

b.

The provisions of Specification 3.0.4 are not applicable.

ACTION 32 With the r; umber of OPERABLE channels less than the Minimum Onan-nels OPERABLE requirement, restore at least one inoperable chan-nel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 i

are not applicable.

ACTION 33 With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, initiate the alternate method of monitoring the parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and either restore the inoperable channel (s) to OPERABLE status within 7 days or prepare and submit a Special Report to the Commission, pursuant to Speci-fication 6.8.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.

The provisions of Specifica-tion 3.0.4 are not applicable.

V0GTLE UNITS - 1 & 2 3/4 3-61 AMENDMENT NO.27 (UNIT 1)

AMENDMENT N0 8 (UNIT 2)

TABLE 3.3-8 (Continued) i ACTION STATEMENTS ACTION 34 -

With the number of OPERABLE channels less than the required num-ber of channels or the Minimum Channels OPERABLE requirement, restore the inoperable channel (s) to OPERABLE status as per Action 31a.a or 31a.b as applicable if repair is feasible during l

plant operation.

If repair is not feasible, prepare and submit a Special Report to the Commission pursuant to Specification.6.8.2 within14daysthatprovidesactIonstaken,causeofthein-operability, and the plans and schedule for restoring the chan-nels to OPERABLE status.

The provisions of Specification 3.0.4 are not applicable.*

ACTION 35 - a. With the number of OPERABLE channels two less than the Total Number of Channels requirement, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

b. With the number of OPERABLE channels three less than the Total Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. With the number of OPERABLE channels less than the Minimum Chan-nels OPERABLE requirement, restore at least one inoperable chan*

nel to OPERABLE status with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months er be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

c. The provisions of Specification 3,0.4 are not applicable.

~ ACTION 36 -

Wit.h tha number of OPERABLE channels less than the Minimum Channels OPERABli requirenrent, comply with the provisions of Specification 3. 0. for an inoperable containment isolatit.n i

valve.

Action Statement 34 applies to the first fuel cycle only.

Action Statement 31a l

is applicable thereafter.

V0GTLE UNITS - 1 & 2 3/4 3-62 AMENDMENT N0.27 (UNIT 1)

AMENDMENT N0.8 (UNIT 2)

--

ML20012B397

Text

Attachment:

Attachment:

Navigation menu

Search