ML20081B487

Application for Amend to Licenses DPR-57 & NPF-5,revising Tech Specs Re Listed TMI Action Plan Items,Per Generic Ltr 83-36

ML20081B487
Person / Time
Site:	Hatch
Issue date:	02/06/1984
From:	Beckham J GEORGIA POWER CO.
To:	Stolz J, Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20081B491	List: ML20081B487 ML20081B501
References
TASK-2.B.1, TASK-2.B.3, TASK-2.F.1, TASK-2.F.2, TASK-2.F.3, TASK-3.D.3.4, TASK-TM GL-83-36, NED-84-034, NED-84-34, TAC-54461, TAC-54462, NUDOCS 8403090187
Download: ML20081B487 (8)

Text

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Georgia Power J. T. Beckham. Jr.

vre neset and oeera r renay, E 84-034 nemy cer a an February 6,1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NTF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST 'ID AMEND TECHNICAL SPECIFICATIONS 'IMI ACTION PLAN ITBIS Gentlemen:

Your letter of November 1, 1983, (Generic Letter 83-36) identified those

'IMI Action Plan items which were scheduled for implementation after December 31, 1981, ' and for which Technical Specification changes were required.

Guidance on the scope of specifications and sample pages in the fomat of the. Standard Technical Specification were provided for informational purposes. Georgia Power Company (GPC) was requested to review Plant Hatch Technical Specifications to determine their degree of consistency with the staff guidance and to submit an application for license amendments where necessary.

GPC h:s ccepleted the requested review and determined the appropriate changes. In acconlance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), GPC proposes to amend the Plant Hatch Units 1 and 2 Technical Specifications- (Appendix A to the Operating Licenses). Pursuant to 10 CFR 50.92, J. L. Ledbetter of the Georgia Department of Natural Resources will be sent a copy of this submittal. The specific chan requested are detailed in Enclosure 1 (msponse to NRC staff guidance) ges and Enclosum 2 (instructions for incorporation of changes) of this letter.

The proposed changes have been reviewed by the Plant Review Board and the Safety Review Board and have been determined not to involve an unreviewed safety question. The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety would not be increased above those analyzed in the FSAR because of the 8403090187 840206 PDR ADOCK 05000321 P PDR g}

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. Dir.sctor of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 February 6,1984 Page Two operation of safety-related equipment is not affected by the proposed changes. The possibility of an accident or malfunction of a different type than eny analyzed ~ in the FSAR would not result from these changes because no new mode of failure is introduced. The margin of safety as defined in the basis for any Technical Specification would not be affected by these changes i because the changes involve additional retrictions not previously included in the Technical Specifications. The proposed changes have been evaluated and determined not to involve significant hazards considerations. This evaluation is doctmented in Enclosure 3.

A determination of caendment class is included as Enclosure 4. We have determined these amendments to be Class III for one unit and Class I for the other unit and _have enclosed the appropriate payment.

J. T. Beckham, Jr. states that he is a Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company and that to the best of his knowledge and belief the facts set forth in this letter are true.

GBORGIA POWER COMPANY by: d J. T. Beckha;a, Jr.'

Sworn to and subscribed before me this 6th day of February,1984.

Notary Public. Cc3rra, S:sta at Large Notary Public My Commaston Expres Aug26,1985 JH/mw Enclosures xc: J.T. Beckham, Jr.

H.C. Nix, Jr.

J.P. O'Reilly (NRC - Region II)

Senior Resident Inspector J.L. Ledbetter

ENCLOSURE 1 NRC DOCKETS 50-321,30-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN 1. IIATOI NUCLEAR PIAYr UNITS 1, 2

_ REQUEST TO A>END TECHNICAL SPECIFICATIONS 'IMI ACTION PLAN ITBtS Georgia Power Company (GPC) response to the NRC staff guidance provided in Generic Letter 83-36 is as follows:

(a) STAFF GUIDANCE - REAC'ILR C00LAN1' SYSTBt VENTS (II.B.1)

'The staff has determined that no changes to Technical Specifications are required by this Action Plan item for Boiling Water Reactors (BWRs) which do not have isolation condenser. The staff has also concluded that no changes in Technical Specifications are required for those plants which have isolation condenser, and either a turbine driven high pressure injection sy., tem or a feedwater coolant injection system with an auxiliary power source such as a gas turbine.

Those BWRs with isolation condenser, and no high pressure injection other than normal feedwater or the control rod drive system must have isolation condenser vents which satisfy the requirements of Item II.B.1 of NUREG-0737. These plants should have at least one reactor coolant system vent path (consisting of at least two valves which are powered from emergency buses) operable and closed at all times (except for cold shutdown and refueling) at isolation condenser high points. A typical Technical Specification for reactor coolant system vents is provided in Enclosure 3."

RESPONSE

Plant flatch has no isolation condensers. Technical Specification charges in response to this item are therefore riot necessary.

(b) STAFF GUIDANCE - POST-ACCIDENT SAMPLING (II.B.3)

" Licensees should ensure that their plant has the capability to obtain and analyze reactor coolant and containment atmosphere samples under accident conditions. An administrative program should be established, implemented and maintained to ensure this capability. The program l

should include:

a) training of personnel .

.i b) procedures for sampling and analysis, and

' c) provisions for maintenance of sampling and analysis equipment It is acceptable to the Staff, if the licensee elects to reference this program in lthe' administrative 1 controls section of the Technical Specifications and include a detailed description of the program in the plant operation manuals. A copy of the program should be readily available to the operating staff during ' accident and transient conditions."

E RESPONSE p -

Item II .B. 3 has not yet been fully implemented at Plant Hatch.

h c Technical Specification cnanges w.11 he add ressed at the time

{ irrplementat ion i s comp.ete. The conpiction schedule is currently being c negotiated by GPC and the NRC staff.

(c) STAFF CUIDANCE - NOELE GAS EFFLUE.V1 MONIInRS (I1.F.1.1) -

" Noble gas ef fluent monitors provide i nf omat ion, du r i ng and followi ng an accident, which are considered helpful to the operator in assecsing the plant condition. It is desired that the se monitors be operable at all times curing plant operation, but they are not re gii red for safe shutdown of the plant. In <ase of failure of the monitor, appropriate ~

actions should be taken to re st o re its opera ti onal capability in a -

. reasonal le peried of time. Consideri ng the importance of the availabf li ty of the equipment and possible delays involved in t_ administrative controls, 7 days is considered to te the appropriate time period to restore the operability of the mcni to r. An alternate method for moid e nring the effluent should be initiated as soon as practical, -

but no later than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> af ter identification of the failure of the I monitor. If the monitor is not restcred to operable condition within 7 days after th . failure , a special report should be submi t ted to the NRC within 14 days folla ing the ( ve nt , onclining the cause of i noperabili ty, actions taken and the planned schedule for restoring the system to operable status."

_RFSPONSE Post-eccident effluent monitors have been installed at the Main Stuk armi the Units ' and 2 Reactor Bui ld i r,g V"nt Pl enum s. These monitors supplement the previously exi v ing nomal range monitors to provide f

noble gas runitorire capability in accordance with Item II.F.1.1.

Enclosure 2 contains proposed revisions to the Units 1 and 2 Technical Specificat'.ons which would add the post-acc ident monitors to the lists .

of accid 9nt menit ori ng instruments. Proposed LCO and surveillance --

requirements are in accordance with the staff guidance.

+ (d) STAFF GUIDANCE - SAMPLING AND ANALYSIS OF PLANT FFFLUENTS (II.F.1.2)

Each operat ing nuclear power reac tor should have the capability to .

collec t and analyze or measure reptuent ative samples of radioactive ,

iodines and particulates in plant gaseous effluents during and following an accident. !w administra+ive prog ram should be established, implemanted and meintained to ensure this capability. The program should include:

a) training of personnel b) procedures for sampling and analysis, and c) provisions for maintenance of sampling and analysis equipment It is acceptable to the Staf f, if the licensee elects to reference this program in the administrative cont rol s section of the Technical Snecifications and include a detailed descriptior of the program in the plant operation manuals. A copy of the program should be readily availalle to the aperating staff duri ng accident and transient 1 conditions."

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RESPONSE

The post-accident effluent monitors which were installed at the Main  ;

Stack and tha Units 1 and 2 Reactor Building Vent Plenue:s also provide  ;

the capability for radioac ti ve iodine and pa rt icula t e sampling in accordance with Item II.F.1.2. Included in Enclosure 2 are proposed  :

revi sions to Units 1 and 2 Adminirtative Technical Specifications which ,

would require an administrative program to ensure post-accident sampl i ng and analysis capability. The proposed changes are in accordance with the staff guidance.

(e) STAFF GUIDANCE - C0KfAINMENT HIG1 RANGE RADI ATION MONITOR (II.F.1. 3)

"A minimum of two in containment radiation-level monitors with a maximum range of 108 rad /hr (107 rad /hr for photon only) should be operabl e __

at all times except for cold shutdown and refueling outages. In case of failure of the monitor, appropriate actions should be taken to re store its operational capability as soon as possible. If the monitor is not re stored to operable condi tion within 7 days after the failure, a special report should be submitted to the NRC within 14 days followi ng the eve nt , outlining the cause of inoperability, accions taken and the r planned schedule for restoring the equipment to operable status.

Typical surveillance a quirer.ents are presented in Enclosure 3. The setpoint for the high radiation level alann should be determined such that spurious ala rms will be prec luded. Note that the acceptable calibration techniques for these monitors are discussed in NUREG-0737."

RESPONSE

In response to Item II.F.1.3, each of the Hatch units was provided with two in-containment gamma radiation monitors having ranges of 1 to 10' R/hr. Enclosure 2 contains proposed revisions to the Units 1 and 2 Technical Specifications which would add these monitors to the lists of accident monitori ng instruments. Proposed LCO and surveillance requirement s are in accordance with the staff guidance. The setpoint for the high radiation alarm is 100 R/hr which is sufficiently higher than the normal containment radiation level to preclude spuri ous ala nns. The calibration method to be used for these monitors complies >

with the guidance provided in NUREG-0737. -

(f) STAFF GUIDANCE - CONTAIhMENT PRESSURE MONITOR (II.F.1.4 )

" Containment pressure should be continuously indicated in the control room of each operati ng reactor duri ng Power Operation and St a rtup Modes. Two channels should be operable at all times when the reactor is operating in any of the above mentioned modes. Technical Specifications for these monitors should be included wi th other accident moni tori ng instrumentation in the present Technical Specifications. Limiting conditions for operation (LCO) for the containment pressure monitor should be similar to other accident moni t ori ng instrumentation included in the present Technical Specifications. Typical acceptable LCO and surveillance requirement s for accident moni t oring instrumentation a re included in Enc losure 3."

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RESPONSE

Each of the llatch units was provided with two channels of high range (0 h to 250 psig) d rywell pressure moni t ori r.g in response to this item. ir These monitors supplement previcusly existing (-10 to +90 psigi  ;-

rrenitors to provide the capability required by Item II.F.1.4. Enclosure &

2 contains proposed mvisions to Units 1 and 2 Technical Specifications g which wuld add the high range pressure monitors to the lists of g accident monitoring i nst niment s. The proposed LCO and surveillance g requirerr.ents a re similar to those t'o r the previou-ly existing d rywel l _

pressure monita s. m (g) STAFI- GUIDANCE - CONTAINMENT WATER LEVEL MONIER (II.F.1. 5) -

L "A continuous ind ica tion of suppression pool water level should be [

provided in the cont rol room of each operating reactor during Power [

Operation and Startup Modes. Two chanrels should be operable at all =

times when the reactor is operating in auy of the above mentioned =

modes. Technical Specifications for suppression pool water level =

monitors shoul d be included wi th other accident moni toring i i nst ru'nentat i on in the p resent Technical Specifications. Limi ti ng -

conditions for operation (LCO) for these monitors should be similar to E other accident monitori ng instrumentation i ncluded in the present -

Technical Specitications. Typical acceptable LCO and surveillance -

requiremeats for accident monitoring instrumentation a re included in Enclosure 3. 4 E

The BWRs with dry containment should have at least two channels for wide 5 range instruments and one channel of narrow range inst niment operable at .

all times during above me ntiorred modes- LCCs for wide range monitors a should be similar to that discussed above. LCOs for na rrow range E moni tor shculd include the requirement that the inoperable hannel will [

be restored to operable status within 30 days or the reactor will be a brought to hot shutdown condition as required by other accident E-moni tori ng i ns trumentation. "

E RESPONSE ,

E Previously existing wide range containmem water level moni tors provide.i g the capability required by Item II.F.1.5 with the exception of =

2nvironmental qualification. The monitors have been upgraded to the ,

appropriate environmental standa rd s . Units 1 and 2 Technical "

Specifications for accident monitoring inst niments currently contain appropriate LCO and surveillance requirements for these monitcrs. [

m er (h) STAFF GUIDANCE - CONTAINMENT HYDROGEN MONITOR (II.F.1. 6) E

'Two indeper> dent containment hyd rogen monitors should be operable (should be capable of p-rfonning the required function) at all times _-

when the reactor is opera ting in Power Operatian and Startup Modes.  ;

Technical Specifications for hydrogen monitors should be included with g other accident monitori ng instrumentation in the present Technical "

Specification. Typical acceptable LCO and surveillance requirements are includcd in Enclo.sure 3." _;

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e RESX)NSE

'l Previously existing containment hydrogen / oxygen monitors provided the capability required by Item II.F.1.6 with the exception of envi ronmental quali fi ca tion. The monitors are presently being modified to meet the appropriate environmental standa rd s. Units 1 and 2 Technical .l Specifications for accident monitoring instruments contain LCO and J surveillance reaui rements Specification amendment proposal for these dated monitors.

December 21, Our 1983 Technical cequests j

y changes to reflect modifications to these monitors. No further changes 4 are considered necessary.

(i) STAFF GUIDANCE - CONIROL ROOM HABITABILITY REQUIRBIENTS (III.D.3.4) j T

" Licensees should assure that cont rol room operators will be adequately ;3 protected against the effects of the accidentM release of toxic and/or g radioactive gases and that the nuclear power plant can be safely y operated or shut down under design basis accident conditions. ff the 4 results of the analyses of postulated accidental release of toxic gases j (at or near the plant) indicated a need for installing the toxic gas j detection system, it should be included in the Technical j Specifications. Typical acceptable LCO and surveillance requi rement s  :

for such a detection system (e.g. chlorine detection system) a re provided in Enclosure 3.

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All detection systems should be included in 3 the Technical Specifications. In addition to the above requ irement s , d other aspec ts of the control room habitability requi rement s should be 4 included in the Technical Specifications for control room emergency air i filtration system. Two independent control room emergency air p filtration system should be operable continuously during all modes of j!

plant operation and capable of meeting design requirements. Sample --

Technical Specifications are provided in Enclosure 3."

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RESPONSE

Our submittal dated December 31, 1980 provided an evaluation of the j Hatch control room habitability wi th respect to the criteria of Item g III.D.3.4. The results of the evaluation indicated that the previously g existing control room air intake chlorine monitors provided the required protection of operators against a toxic gas release. Technical 1 Specifications for the chlorine monitors and the control room emergency  ?!

filtration systems were discussed in the evaluation. The NRC letter dated March 9, 1982 transmitted a Safety Evaluation in which the GPC position on Itan III.D.3.4 was accepted.

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NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST 10 AMEND TBCINICAL SPECIFICATIONS-TMI ACTION PLAN ITB6

. The proposed changes to. Unit .1- Technical . Specifications (Appendix A to

Operating License DPR-57) would be incorporated as follows:

Remove Page- Insert Page -

3.2-22 3.2-22 3.2-22a.

3.2-23 3.2-23 3.2-23a

3. 2-48a

' 3.2-49 3.2-49 3.2-68 3.2-68 6-22

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