Text

Amend 91 to License NPF-5,modifying Tech Specs to Permit Hydrostatic & Leak Testing W/Noncritical Reactor Core
	ML20150C214
Person / Time
Site:	Hatch ; (NPF-05-A-091, NPF-5-A-91)
Issue date:	03/12/1988
From:	Jabbour K; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20150C217	List: ML20150C214; ML20150C224; ML20150C233;
References
	TAC-66947, NUDOCS 8803180072
	Download: ML20150C214 (11)
	v • d • e

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UNITED STATES 3 sey {1 l g

NUCLEAR REGULATORY COMMISSION y

WASHINGTON, D. C. 20555 5,

\\...../

GEORGIA POWER COMPANY O_GLETHORPE POWER CORPOPATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH N'ICLEAR PLANT, UNIT '40. ?

AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-5 1.

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

A.

The application for 6mendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated January 4, 1988, complies with the standards and requirements cf the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules ar.d regu-letions 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 (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 tha Comission's regulations set forth in 10 CFR CnspterI; D.

The issuance of this amer.dment 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 CFP Part 51 of the Comission's regulations and all applicable recuirements have been satisfitd.

Be03100072 800312 PDR ADOCK 05000366 P

PDR m

, 1 2

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

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendaent No. 91, 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 C0iellSSION Original signed by:

Kahtan N. Jabbcur, Acting Director Project Directorate 11-3 Division of Reactor Projects-I/II i

Attachment:

Changes to the Technical Specifications Date of Issuance:

March 12, 1988

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ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO.,50-366 Replace the following pages of the Appendix A Tf chnical 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 1-11 1-11 3/4 3-12 3/4 3-12 3/4 3-15 3/4 3-15 3/4 6-36 3/4 6-36 3/4 6-37 3/4 6-37 3/4 6-40 3/4 6-40 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2

4 TABLE 1.2

~

OPERATIONAL CONDITIONS MODE SWITCH AVERAGE REACTOR CONDITI,0N POSITION COOLANT TEMPERATURE 1.

POWER OPERATION Run Any Temperature 2.

STAATUP Startup/ Hot Standby Any Temperature 3.

HOT SHUTDOWN Shutdown

> 212*F***

4.

COLD SHUTDOWN Shutdown s 212'F***

5.

REFUEL.ING*

Refuel **

s 212*F l

l 1

i Reactor vessel head unbolted or removed and fuel in the vessel.

See Special Test Exception 3.10.3.

j

- - During the performance of inservice hydrostatic or leak testing with all l

control rods fully inserted and reactor coolant temperature above 212*F, the reactor may'be considered to be in the COLD SHUTDOWN condition for the purpose of determining Limiting Condition for Operation applicability.

However, compliance with an ACTION requiring COLD SHUTDOWN shall require a reactor coolant temperature 5 212*F.

In addition, compliance with the following Specifications is required when performing the hydrostatic and l

leak testing under the identified conditions:

3,6.5.1, 3.6.5.2, 3.6.6.1, and 3.7.1.1.

HATCH - UNIT 2 1-11 Amendment No. 91

s TABLE 3.3.2-1 (Continued) g ISOLATION ACTUATIOII INSTRUML1TATIOsl y

7 VALVE CROUPS MINIMUM 8Ht*4tl[R APPitCABit OPERAIED BY OPERABLE CHAfeMER.S OPERATIONAL IRIP f U80CIloss SIGNAL (e)

PER IRIP SYSTEM (b)(c)

C000DaiION ACTIO90 2.

StCOceDARY CONIAfleMENT iSOLAiION m

a.

Reactor Building Exhaust Radiation - High 6, 10, 12,

2 1,2,3,5, 24 (2011-k609 A, 8, C, D)

a nd * *

F b.

DryweI I Pressure - High 2, 6, 7, 10, 2

1, 2, 3

24 (2Cil-le6SO A, 8, C, D) 12,

c.

Reactor vessel Water level - t ow Low (LMel 2) 5, 2

1, 2, 3

24 (2821-88682 A, R, C, D) and m d.

Refueling flot r [xhaust Red:ation - High 6,

10, 12, 2

1,2,3,5 24 (2011-k611 A, 8, C, D)

a nd * *

3.

REACTOR WATER CLEAteUP SYSTEM ISOLAllON ts1 m.

A Flow - High (2C31-N603 A, D) 5 1

1, 2, 3

25 Y

b.

Area Temperature - High 5

1 1, 2, 3

25 (2C31-fe662 A, D, E H, J, M)

N c.

A res Ven t i l a t i on A T emp. - High 5

1 1, 2, 3

2$

(2C31-II663 A, D,

E, H, J, M; 2C31-18661 A, D, E,H J,M:

2C31-80662 A, D, E, II, J, M) d.

SLCS Initiation (NA) 5

NA 1, 2, 3

25 e.

Reas: tor Vessel Water tevel - L ow l ow S*

2 1, 2, 3

2$

(Level 2) (2821-81682 A, 8, C, D)

N E.

Ea r0 if C.

N Y

s R

4

7ABLE L 3.2-1 (Cnaticued) f$0La7!0N ACTUAT?CN IN5?AL98ENTATION

]Q A

ACTION 20 Be in at least HOT $kUTOC%N within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO $HUTOCWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTICN 21 Be in at least $TARTUP with :he main steam line isolation <alves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or to in at least m0T SHUTOC'.N witnin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLO $NUICCnN within tne next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

I ACTION 23 Se in at least STARTUP with the Group 1 isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HOT $ HUT 00WN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 Establish $ECONCARY CONTAINNENT INTEGRITY with the :taneby gas treatment system operating within one hour.

ACTION 25 Isolate the reacto wa'er cleanup system.

ACTION 26 Close the affected system isolatton valves and declare the affected system inoperable.

ACTION 27 verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or close the affected system isolation valves and declare the affected systee Inoperable.

ACTION 28 Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam dome pressure s 145 psig.

ACTION 29 Either close the affected isolation valves within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in het shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

NOTES Actuates the standby gas t eatment system.

When handling irradiated fuel in the se:endary coetainment.

When performing inservice hydrostatic or leak testing with the reactor coolant temperature aMve 212*F.

See $pecification 3.6.3, Table 3.6.3-1 for valves in each valve group.

a.

b.

A channel may be placed in t.n inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one other CPERABLE channel in :ne same trip systee is monitoring that parameter.

c.

With a design providing only one channel per trip systee, an incoeracle chann,el need not be placed in the tripped condition where this woule cause j

the T+1p Function to occur. In these cases, the inocerable channel shall l

be restored to CPE UBLE statue within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by l

Table 3.3.2-1 for that Trip Function small be taken, d.

Trips the mechanical vacuum pumps.

e.

A channel is CPER.ABLE if 2 of 4 instruments in that channel are CPEUBLE.

l f.

May be bypassed with all turbine stop valves closed, f

g.

Closes only RWCU cutlet isoletion valve 2G31-F004, h.

Alare only.

{

1.

Adjusttb.3 go to 60 minutes.

I j.

Isolades containment surge and vent va aes.

HATCH - UNIT 2 3/4 3-15 Amendment No. 91 i

CONTAfNMENT SYSTEMS 3/4.6:5 SECONDARY, CG4TAINMENT SECONDARY CONTMNMENT INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.5.1 Hatch-Unit 2 SECONDARY CONTAINMENT INTEGRITY and Hatch-Unit I secondary containment integrity shall be maintained.

APPLICABILITY: CONDITIONS 1, 2, 3, and *.

l ACTION:

Without Hatch-Unit 2 SECONDARY CONTAINMENT INTEGRITY and/or without Hatch-Unit i secondary containment integrity, restore Hatch-Unit 2 SECONDARY CONTAINMENT INTEGRITY and Hatch-Unit 1 secondary containment integrity within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.5.1.1 Hatch-Unit 2 SECONDARY CONTAINMENT INTEGRITY shall be demon-strated by:

a.

Verifying at least once per 31 days:

1.

All equipment hat,ches are closed and sealed, and 2.

At least one door in each access to the secondary containment is clo:ed, b.

Verifying at least once per 92 days that each secondary contain-ment ventilation system automatic isolation damper is OPERABLE or serured in the closed position per Specification 3.6.5.2.

c.

At least once per 18 months:

1 1.

Verifying.that one standby gas treatment subsystem will l

draw down the secondary centainment to 21/4 inch of vacuum water gauge in s 120 seconds, and 2.

Operating one standby gas treatment subsystem for one hour and maintaining 2 1/4 inch of vacuuc wat1r gauge in the seconcary containment at a flow rate not exceeding l

4000 CFM.

i 4.6.5.1.2 Hatch-Unit I sacendary centainment integrity shall be demon-strated per Hatch-Unit 1 Technical Specifications.

l

When performing inservice hydrostatic or leak, testing with the reactor i

coolant temperature above 212'F.

HATCH - UNIT 2 3/4 6 95 Amendment No. 91

CCNTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION OAMPERS LIMITING CONDITION FOR OPERATION 3.6.5.2 The secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.2-1 shall be OPERABLE.

APPLICABILITY:

CO.'10!TIONS 1, 2, 3, and *.

ACTION:

With one or more of the secondary containment ventilation system automatic isolation dampers s?ecified in Table 3.6.5.2-1 inoperable, operation may continue and the provisions of Specification 3.0.4 are not appitcable, provided that at least one isolation damper is maintained OPERABLE 'n each affected penetration that is open, and; The inoperable damper is restored to OPERABLE status within 8 a.

hours, or b.

The affseted penetration is isolated by use of a closed damper within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or SECONDARY CONTAINMENT INTEGRITY is demonstrated within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months c.

and the damper is restored to OPERABLE status within 7 days.

Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or SURVEILLANCE REQUIREMENTS 4.6.5.2 Each secondary containment ventilation system automatic isolation damper specified in Table 3.6.5.2-1 shall be demonstrated OPERABLE:

At least once per 92 days by cycling each automatic damper 2.

testable during plant operation through at least one complete cycle of full travel.

IWhen performing inservice hydrostatic or leak testing with the reactor coolant temperature above 212'F.

HATCH - UNIT 2 3/4 6-37 Amendment No 91

CONTAINMENT SYSTEMS 3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL STAN08Y GAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.6.1 Two Hatch-Unit 2 independent standby gas treatment subsystems and two Hatch-Unit 1 independent standby gas treatment subsystems shall be OPERABLE.

APPLICABILITY:

CONDITIONS 1, 2, 3, and *.

ACTION:

With one of the above required standby gas treatment subsystems a.

inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the ne'.t 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLO SHUT 00VN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b.

With two or more of the above required standby gas treatment subsystems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.6.1.1 Each Hatch-Unit 2 standby gas treatment subsystem shall be demonstrated OPERABLE:

By initiating, from the control room, flow through the HEPA a.

filters and charcoal adsorbers and verifying that the system operates for at least a total of 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months each 31 days with the heaters on automatic control, b.

At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber nousings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

1.

Verifying that the cleanup system satisfias the in-place testing acceptance criteria and uses tne test procedures of 4egulalory Positions C.S.a. C.5.c and C.5.d of Regula-tory Guide 1.52, Revision 1, July 1976, and the system i

flow rate is 4000 + 0, -1000 cfm.

l 2.

Verifying within 31 days after removal that a laboratory analysis of a representative carbon samole obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 1, July 1976, meets the laboratory

' testing criteria of Regulatory Position C.6.a of Regula-tory Guide 1.52. Revision 1, July 1976.

"When performing inservice hydrostatte or leak testing with the reactor coolant temperature above 212'F.

HATCH - UNIT 2 3/4 6-40 Amendment No. 91 4

~

3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS RESIOUAL HEAT REMOVAL SERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.1 Two independent Residual Heat Removal Service Water (RHRSW)

System subsystems shall be OPERABLE with each subsystem comprised of:

a.

Two OPERABLE pumps, and

- b.

An OPERABLE flow path for heat removal capable of taking suction from the intake and transferring the water through an RHR heat exchanger, APPLICABILITY: CONDITIONS 1, 2, 3, 5, and *.

ACTION:

a.

In CONDITION 1, 2 or 3:

1.

With one RHRSW pump inoperable, operation may continue and the provision's of Specification 3.0.4 are not appli-cable; restore the inoperable pump to OPERABLE status within 30 days or be in at least HOT SHUT 00WN within the next 12 hour-.nd in COLD SHUT 00WN witnin the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2.

With one RHRSW pump in each subsystem inoperable, opera-tion may continue and the provisions of Specification 3.0.4 are not applicable; restore at least one inocerable pump to OPERABLE status within 7 days or be in at least l

HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

I 3.

With c.,e RHR$W subsystem inoperable, restore the inoperable subsystem to OPERABLE status wi.th at least one OPERABLE pump Ivithin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTOCWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

With both RHR$W subsystems inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and either be in COLD SHUTOOWN or maintain the reactor coolant system temperature < 400*F by use of alternate heat removal methods within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

"When performing inservice hydrostatic or leak testing with the reactor coolant temperature above 212'F.

HATCH - UNIT 2 3/4 7-1 Amendment No. 91 w

w---A

PLANT SYSTEMS LIMITING CONDITION FOR "pERATION (Continued)

ACTION (Continued) b.

In CONDITION 5, with up to 3 RHRSW pumps inoperable or with one RHRSW subsystem inoperable, restore both subsystems with at least one pump in each system to OPERABLE status within 7 days or declare the RHR system inoperable for decay heat removal and reactor coolant circulation and take the ACTION required by Specification 3.9.12.

,c.

In condition *, with up to 3 RHR$W pumps inoperable or with one RHRSW subsystem inoperable, restore both subsystems with at least one pump in each system to OPERABLE status within 7 days or be in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.1 Each residual heat removal service water system subsystem shall be demonstrated OPERABLE:

At least once per 31 days by verifying that each valve in the a.

flow path that is not locked, sealed or otnerwise secured in position, is in its correct position, and b.

At least once per 92 days by verifying that each pump develops a discharge prassure of 2 300 psig at a flow of 2 4000 gpm.

1 HATCH - UNIT 2 3/4 7-2

^**"d**"' "

_

v t e Letter Sequence Other
TAC:66947, (Approved, Closed)
Initiation Request, Request Acceptance... Administration Meeting Questions Answers Results Approval, Approval Other: ML20150C214, ML20151C970, ML20235A395
MONTHYEAR1988-01-04 [Table View]

Person / Time
ML20150C214
Site:	Hatch (NPF-05-A-091, NPF-5-A-91)
Issue date:	03/12/1988
From:	Jabbour K Office of Nuclear Reactor Regulation
To:
Shared Package
ML20150C217	List: ML20150C214 ML20150C224 ML20150C233
References
TAC-66947, NUDOCS 8803180072
Download: ML20150C214 (11)
v • d • e

ML20150C214

Text

Attachment:

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