ML20080T271

Amends 98 & 35 to Licenses DPR-57 & NPF-5,respectively, Revising Tech Specs to Extend Time Allowed to Restore Thermal Power Scram & Control Rod Block Trip Setpoints within Tech Specs Limits

ML20080T271
Person / Time
Site:	Hatch
Issue date:	02/22/1984
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA
Shared Package
ML20080T274	List: ML20080T271 ML20080T282
References
TASK-1.A.1.3, TASK-TM, DPR-57-A-098, NPF-05-A-035, TAC 48296, TAC 49071, TAC 49072, TAC 49263, TAC 51392, TAC 51393 NUDOCS 8403010124
Download: ML20080T271 (15)

Text

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4 UNITED STATES j'

, [o NUCLEAR REGULATORY COMMISSION J

WASHINGTON, D. C. 2C555 g, y o r

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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 AMENDENT TO FACILITY OPERATING LICENSE Amendment No. 98 License No. DPR-57 l.

The Nuclear Regulatory Ccmmission (the Ccmmission) has found.that:

A.

The applications for amendment by Georgia Power Company, et al.,

(the licensee) dated June 11, 1982, as corrected October 15, 1982; and March 31, 1983, comply with the standards and requirements of

' the Atomic Energy Act of 19C4, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; E.

The facility.will operate in conformity with the applications, 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;

-0. -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 L

'51 of the Commission's regulations and all applicable requirements have been' satisfied.

' 2. ' Accordingly, the license is amended by changes to the Technical Spec-tifications 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:

Technical' Soecifications The Technical Specifications contained in Appendices A and B, as' revised through~ Amendment No. 98, are hereby incorporated in the license.. The licensee shall operate the facility in

'accordance with the Technical Specifications.

8403010124 840222 PDR ADCCK-05000321 P-PDR

' 3.

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

r FOR THE NUCLEAR REGULATORY COMMISSION o

i F. Stolz, Chief 0 rating Reactors B nch #4 ision of Licensir.g

- Attachment;

, Changes to.the Technical Specifications

'Date~of Issuance:

February 22, 1984 O

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ATTACHMENT TO LICENSE AMENDMENT NO. 98 i

FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 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 a vertical line indicating the area of change.

Remove

' Insert-6-4 6-4 6 11 6-11

+

b e

~

TA3LI 6.2.2-1 MINIML'M SMITT CPIJ COMPOSITIONd C=nditien of Unit 1 - Unit 2 in Reactor Power Oneratien, Hot Standhv er Het Shutdown Conditien APPLICA3LE LICENSI OPERATIONAL CONDITIONS CAYIGORY' 1, 2, 3 4&5 2

2=

SQL**

l 3

3 OL**

3 3

Non-Licensed a

j hh11t iechnical ACV1sor Condition of Unit 1 - Unit 2 in Cold Shutdown Cendition

.or Refuel Mode A??L!O.'2LE e9 LICINSI OPERATIONAL COhTITIONS CATIGORY 1, 2, 3 4&5 I

2 la SOLa*

l 2

OLa*

q 3

3 Non-Licensed 1

None l

Shif t Technical Advisor n

Cendition of Unit 1 - No Fuel in Unit 2 APPLICABLE LICINSI OPI?J !CNAL CONDITIONS

'CATIGORY-1, 2, 3 4&5 SOL 2

1.*

~

3 2

ut Nen-Licensed

.3 3

Shift Technical Advisor 1

Ncne l

s include the Licensed Senior Reactor Operator or Senior Reactor "Does net CORI ALTIF.ATIONS.

Operator Li=ited to Tuel Handling, supervising

• • Assu=es each individual is licensed on both units.

1. Shift crew ce:positien,. including in individual qualified in radiation prctecticn procedures =ay be less than the =ini=um requirements for a period of ti=e not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to acco==edare unexpected absence of en duty shift crew me:bers provided insediate action-is taken to restore the shift crew ce=posjtion to within the

-tini=== requirements of Tab;e 6.2.2-1.

PLANT HAICH l' NIT I 6-4

_Amendscot No. ff, /J, 98

.. ~

E

. :D >it:I s

7. : v ccsTR c u i

AU::ITS 6.5.2.S' Accits of unit activities shall ce perfcmec uncer the cognizan e of the SRE.

Eacn inscection er au::it snali ce perfcrmsd within the s;iecified

-time interval witn:

1.

A maximum allowable extension not to exceed 25.v. of the inscection or audit interval.

2.

A total maximum combined interval - time f,or any 3 consecutive inspection or audit intervals not to exceed 3.25 times the specified inspection or audit interval.

-These audits shall encompass:

a.

The conformance of unit operation to provisions contained within the Technical Specifications and applicable license conditions at

, least once per 12 months.

- b.

'The perfomance, training and qualifications of the entire unit staff at least once per 12 months.

c.

The.results of actions taken to correct deficiencies occurring in

-unit equipment, structures, systems 'or method of operation that affect nuclear safety at least once per 6 sonths.

d.

The performance of activities required by the Coerational Quality

~

Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

~

e.

The Emergency Plan and implementing procedures at least once per 12 months. shall be perfomed by individuals who have no direct resconsibility for implementation of this plan.

f.

The Security Plan and implementing procedures at least once per 12 months shall be performed by individuals. who have no direct responsibility for implementation of this plan.

g.

Any other area of unit operation considered appropriate by tne SRB or the Senior Vice President Power Supply.

.h.

The Fire Protection Procram and implementing procedures at least once per 24 months.

1.

An independent fire protection and loss prevention inspection and audit shall be perfomed annually utilizing either qualified offsite. licensee personnel or an outside' fire protection fim.

-j.

An inspection and audit of the fire protection and loss prevention program shall be perfomed by an outside qualified fire consultant at' intervals no greater than 3 years.

During the year in which the inspection er audit occurs. the requirements of 6.5.2.81 can be affected concurrently.

AUTHORIT/

6.5.2.9 The SRS shall repcrt to and advise the Executive Vice President -

Power. Stcply on those areas of responsibility specified in Sections 6.5.2.7 anc 6.5.2.8.

HAT:H '- UNIT 1 6-11 Amen 6ent No U, D,98

)

Mmecg\\

UMTED STATES

.,, g y..., [ g NUCLEAR REGULATORY COMMISSION g,g E

WASHING TON, D. C. 20555

% y', j;g 3 71 GEORGIA POWER COMPANY P

OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGI A CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT. UNIT N0. 2 A5NDMENT TO FACILITY OPERATING LICENSE Amendment No. 35 Licerce No. NPF'-5 1.

The Nuclear Regulatory Commission (the Cc=ission) has found that:

A.

The apf.ications for amendment by Georoia Power Company, et al.,

(the licensee) dated April 5,1982; June 11,1982, as corrected October 15, 1982; November 10, 1982; and March 31, 1983, comply 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 confamity with the applications, the provisions of the Act, and the rules and regulations of tne Ccmmission; C.

There is reasonable assurance (i) that the activities authorized by this amencment 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 oefense 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 cf the Comission's regulations and all applicable requirements have been satisfied.

-2.

Accordingly, the license is amended by changes to:the Technical Spec-

-ifications.as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

Technical Soecifications

.The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 35, are hereby incorporated.

.in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

2-3.

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

FOR THE tiUCLEAR REGULATORY COMMISSION

//

hn F. Stolz, Chief 8

pe ating Reactors Branch #4 vision of Licensing

Attachment:

- Changes to the. Technical Specifications

.Date.ofLIssuance: February 22, 1984 4

A e

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e-9 4

5

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ATTACHMEtiT TO LICEllSE AMEliDMEliT tiO. 35 FACILITY OPERATIt!G LICEll5E fiO.11PF-5 DOCKET 110. 50-366 Replace the following pages of t' e Appendix "A" Technical Specificaticns h

with.the enclosed pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

The corresponding _ overleaf pages are also provided to maintain document completeness.

Recove Insert-3/4 2-5 3/4 2-5 3/45-9' 3/4 5-9 6-4 6-4 10.

6-10 4

4

{:

4

=

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POWER DXSTRIEUTTON LIMITS '

~

3/4.2.2 ' APPJ1 SETP01 HTS LIMITING CONDITIO.'! FOR OPERATION 3.2.2 The APRM flow referenced simulated thermal power scram trip set-point (S) and control rod block trip setpoint (SRB) shall be established *-

according to the following relationships:

5 < (0.66W + 51%)

gg,<_ (0.66W + 421)

S where: S and S are in percent of RATED THERMAL POWER, and W = Locpep' recirculation flow in percent of rated flow.

APPLICABILITY:

CONDITION 1, when THERMAL POWER > 25% of RATED THERMAL POWER.

ACTIO":

1ith 5 or Sn exceeding the allowable value, initiate corrective action within 15 mYriutes and continue corrective action so that 5.and S, are within the reouired limits

• within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or reduce THEFFAL POW l

less than 25% of PATED THERMAL PDWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

~

4 EURVE1LLANCE PE0JIREMENTS a.2;2 The CMFLPD shall be determined and the APRM flow referenced simulated thermal power scram and control rod block trip setpoints or APRM readings adjusted, as required:

a.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

Whenever THERMAL POUER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, and Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is c.

operating with a CMFLPD > FRTP.

• l'ith CORE MAy.!MJM FRACTION OF LIMITING POWER DENSITY (CMFLPD) greater than the fraction of RATED THERMAL POWER -(FRTP), RA D

'4 R '

up to 95% of RATED THERMAL POWER, rather than adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM recdinos are areater than or ecual tc 100! times CMFLPD, provided that the adjusted APRM reading does not exceed.100L of RATED THERMAL POUER and the rec;uired gain adjustment increment does not exceed 10% of RATED THERMAL POWER.

HATCH - UNIT 2 3/4 2-5 Amendment flo. N, 35

3/4.2.3 MINIMLf4 CRITICAL FOhER RATIO

)

t LIMITIPC CONDITICN FOR 0:E ATION 7e 3.2.3 The MINIMUM CRITIC 5L F0hER FATIO ' (K.:R ), as a function of average scram time and core flow, shall be ecual to or greater than shown in Figure 3.2.3-1, Figure 3.2.3-2 or Figure 3.2.3-3 multiplied by the Kr shown in Figure 3.2.3-4, where:

~

^

( Lave LB), whichever is greater, t

0 or

=

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L A -La T

= 1.096 see (Specif1:stien.3.1.3.3. scram time limit to A

noten 36),

9.

T a = 0.834 l.65 [

Ni

]~(0.059),

(

n< n1 n

is E

~

N Tt

.U ave =

'*1 t

D7 Ng m..

= number of surveillance tests performed to date in cycle, n

i N

i = ru ber of active ccntrol reds measured in the i h su veillance t

test, Ti = average scram time to notch 36 of all rods measured in the itA surveillance test, and N1 = total num er of active rods measured in 4.1.3.2.a.

A:FLICABILITY: CCNDITION 1, when THERFAL FOtER 2 25% R;iTED THER.L'AL FOtER ACTICN:

With FCFR less than the acclicable limit cetermined from Figure 3.2.3-1, Figure 3.2.3-2 cr Figure 3.2.3-3, initiate corrective E: tion -ithis 15 l

minutes and continue corrective action so that MCFR is e:ual t0 c: greater than the applicable limit within 2 hcurs or reduce THERt'AL FChER to less than 25% of RATED THERVAL FOKER within the next 4 hcurs.

EURV ILL AFCE ::CUI:EkENTS 4.2.3 The tCFR limit at rated flow shall be determined for each tyce of fuel (BXSR, FBXER, and 7X7) from Figures 3.2.3-1, 3.2.3-2, and 3.2.3-3 using:

T = 1.0 prict to the initial scram time measurements ft:

a.

t e cycle perfo meo in accorcance with Specification 4.1.3.2.a, ::

FATCH - UNIT 2 3/4 2-6 A en:: en Nc. 27, 33 h

... E"ERGENCY CO?E C00 lit:G SYSTE"5 3/4.5.4 SUPPRESSION CHA"3ER

~

LIMITING CONDITION FOR OPERATION -

3.5.4 The suppression chamber shall be OPERABLE with a minimum i

contained water volume of 653,000 gallons, equivalent to a level of 12'2",' and the water level. instrumentation channels alarms adjusted

- to actuate at a low water level > 12'2", except that the suppression chamber may be drained:

-a.

In OPERATIONAL-CONDITION 4, provided that; 1.

No work is performed which has a potential for draining the reactor vessel, 2.

The reactor mode switch is locked in the Shutdown position, and 3.

The core spray system is OPERABLE per Specification 3.5.3.1 with an OPERABLE flow path capable of taking suction from the OPERABLE condensate storage tank and -

transferring the water through the spray sparger to the react 6r vessel.

b.

In OPERATIONAL CONDITION-5, provided that the ~ reactor mode switch is locked in the Refuel position, and:

1.

The core spray system is CPERABLE per Specification 3.5.3.1 with an OPERABLE flow path capabic of taking suction from the OPERABLE condensate storage tank and transferring the water through the spray sparger to the reactor

. vessel, or 2.

The reactor vessel head is removed and the cavity is flooded, tne spent ~ fuel pool gates are removed, and the water leval-is maintained within-the limits of Specifica-tions _3. 9. 9 and 3.9.10 l

APPLICABILITY:

CONDITION 1, 2, 3, 4 and 5.

ACTICN:

a.

_In CONDITION 1, 2 or 3 with the sup:ressien chamber water

~

level less than tne above limit, restore the water level tc within the -limit within I hour or be in at least HOT SHUTD0'!N within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDC'.:N within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.:

b.

In CONDITION 4 or 5 with the suppression chamber drained and the conditions of Specification 3.5.4.a or 3.5.4.b, as app'.icable,. not satisfied, suspend all ocerations in tne reactor vessel and all positive reactivity changes. The provisions of Specificatien 3.0.3 are not a;olicable.

Hr.TCH - UNIT 2 3/4 5-9 Amendment No. E, 35

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L HATCH - UNIT 2 6-3

l l

TABLE'6.2.2-1 r.

MINIMUM SHIFT CREW COMPOSITION #

Condition of Unit 2 - Unit 1 in Reactor Power Goeration, Hot Stanoby or Hot Snutoown Conoition

. LICENSE APPLICABLE CATEGORY OPERATIONAL CONDITIONS 1,2,3 4&5 50L**

2 2*

l OL**

3 3

Non-Licensed 3

3 Shift Tecnnical Advisor 1

1 Condition of Unit 2 - Unit 1 in Cold Shutdown Condition or Refuel Mooe LICENSE APPLICASLE CATEGORY OPERATIONAL CONDITIONS 1, 2. 3 4&5 50L**

2 l'

(

OL**

3 2

Non-Licenseo 3

3 Snift Tecnnical Aovisor i

None Condition of Unit 2 - No Fuel in Unit 1 LICENSE APPLICASLE CATEGORY OPERATIONAL CONDITIONS 1, 2, 3 4&5 50L**

2 l'

OL**

3 2

Non-Licenseo 3

3 Shift Tecnnical Aovisor 1

hone Does not include the Licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling, supervising CORE ALTERATIONS.

Assumes each individual is licensed on both units.

1. Shift crew' composition, including an individual qualified in radiation protection procedures, may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements

.of Table 6.2.2-1.

PLANT HATCH UNIT 2 6-4 Amendment Ho. JE, 35

ADMINISTRATIVE CONTROLS T

QUORUM 6.5.2.6 The minimum quorum of the SRB necessary for the perfomance of the SRB review and audit functions of these Technical Specifications shall consist of the'Chaiman or Vice Chaiman and at least 3 SRB members.

No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW I-6.5.2.7 The SRB shall review:

a.

The_ safety evaluations for (1) changes to procedures, equipment or systems and (2) tests 'or experiments completed under the

. provision of Section 50.59, 10 CFR, to verify that such actions

~did not constitute an unreviewed safety question.

b.'-

Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.

Proposed tests or experiments which involve an unreviewed c.-

safety question as defined in Section 50.59 10 CFR.

d.

Proposed changes to Technical Specifications or this Operating License.

e.

Violations of codes, regulations, orders. Technical-Specifications, license. requirements, or of internal procedures or instructions having nuclear safety significance.

f.

Significant operating abnormalities or deviations from nomal and expected performance of unit equipment that affect nuclear safety.

g.-

Events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Comission.-

h.

All-recognized indications of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.

1. _

Reports _and meetings minutes _of the Plant Review Board.

3-A HATCH - UNIT 2 6-9

TO 9..

--.v: CCN :0_F

'AUO:TS 6.5.2.8. Audits of unit activities snall be perfcmed uncer the ec;nizance of the SRE.

Each insoection or audit - snall be performed within the soecified time. interval with:

-1..

A ' maximum allowable extension not to exceed 25% of the inspection or audit interval..

2.

A total maximum combined interval time for any 3 consecutive inspection or audit intervals not 'to exceed 3.25 times the specified inspe'etion or audit interval.

LThese audits shall encompass:

a.

The conformance of unit operation to provisions contained within the. Technical Specifications and soplicable' license conditions at e least once per 12 months.

- b.

The performance, training and qualifications of the entire unit staff at least once per 12 months, c.- ; The results-of actions taken to correct deficiencies occurring in unit. equipment, structures, systems or method of operation-that affect nuclear safety at least once per 61nonths.

d.

The performance of activities rec = ired by the Operational Quality Assurance Program to meet the criteria of Appendix "B",10 CFR 50, at least once per 24 months.

e.

The Emergency Plan and implementing procedures at least once per 12

-mcnths. shall be performed by individuals who. have 'no ' direct responsibility for implementation of this plan ~.

f.

The Security Plan and imolementing procedures at least once per 12 months shall be performed by individuals who. have no direct responsibility.for implementation of this plan.

~

.g.

Any. other area of unit operation considered scoropriate by the SRB or the Senior Vice President Power Supply, h.

The Fire Protection Program - and ' implementing procedures at least once per 24 months.

'i.

An independent fire protection and l'oss prevention inspection and audit shall be performed annually. utilizing either cualified offsite licensee personnel or an outside fire protection firm.

L j.- ' An inspection and audit of the - fire protection and loss prevention

' program shall be perfomed by an outside ouslified fire consultant at intervals no greater than 3 years.

During the year--ih which the

= - '

inspection cr audit occurs,. the recuirements of 6.5.2.81 can be affected concurrently.

AUTHORITY' 6.*5.2.9 Th SRB ~shall report to and advise the Executive Vice President -

Power Stoply on those areas of responsibility specified in Sections 6.5.2.7 7 t 6.5.2.8.

kaendment No. 7E,35

' HATCH - UNIT 2 6-10

_ _ _ - - _ - _