ML20030A857

Order Confirming Licensee Commitments Re post-TMI Related Requirements of NUREG-0737.Requests That Applicant Satisfy Specific Requirements of Nureg,Described in Attachment, within 30 Days

ML20030A857
Person / Time
Site:	Maine Yankee
Issue date:	07/10/1981
From:	Eisenhut D Office of Nuclear Reactor Regulation
To:	Maine Yankee
Shared Package
ML20030A855	List: ML20030A854 ML20030A857
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-***, TASK-TM NUDOCS 8107290096
Download: ML20030A857 (10)

Text

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,1 7590-Of.

UNITED STATES CF AMERICA NUCLEAR REGULATORY COMMISSION

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In the Matter of

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Docket No. 50-309

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itAINE YANKEE ATOMIC POWER C0ftFANY

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(Maine Yankee Atomic Po,cer Diant)

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ORDER CONFIRMING LICENSEE COMMITMENTS ON POST-TMI RELATED ISSUES I.

Maine Yankee Atomic Power Company (the' licensee) is the holder of Facility Operating Licensa No. DPR-36, which authorizes the operation.of Maine Yar.kee Atomic Power Station (the facility) at steady-state power levels not in excess of 2530 megawatts therms 1.

The f acility consists of a pressurized water reactor (PWR) located at the licensee's site in Lincolt County, Maine.

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Followthg the accide,t at Three Mile Island Unit No. 2.lMI-2) on March 28, 1979, the Nuclear Regulatory Cemmission (NRC) staff developed a number of 1

l proposed requirements to be implemented on operating reactors and on plants under construction. These requirements inclade Operational Safety, Siting and Design, and Emergency Preparedness and are intended to provide substantial additional protection for the operation of nuclear facilities based on the i

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- i axperience from the accident at-TMI-2 and the official studies and investi-gations of_the accident. The staff's proposed requirements and' schedule;for

- implementation are. set forth.11 NUREG-0737, " Clarification of TMI. Action -

Plan Requi.rements." among these requirements are a number of items,- con -

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sisting of nardware modifications, administrative procedure implementation and specific information to ~be suomitted by the. licensee," scheduled to be -

completed on or before June 30,1981 (see. the Attachment, to this Order). -

- NUREG-0737 was transmitted to each 1icensee andipplicant by an NRC letter-from my office dated October 31, 1980 which 's hereby incorporated by reference.

In that letter, it was. indicated that although the NRC staff expected each requirement to be implemented in accordance with the schedule set forth in NUREG-0737, the staff would consider licensee requests for relief from staff proposed requirements and.their associated implementa-tion dates.

1 III.

The licensee's submittals dated December 15, 1980, and January 8,16, and 30-,

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March 11 and 16,1981 and the references stated therein, which are. incorporated

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.herein-hy_ reference, committed to complete each of the actions specified in the Attachment. The licensee's subrittals included a modified schedule for subm'ttal of-certain information. Tne staff has reviewed the licensee's-submittal and determined that the licensee's modified schedule i_s acceptable based on the folicwing:

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'The licensee's ' schedule for submittal of information in -

soce-instances does not. meet > the,' taf f's specified s

submittal dates. Most of the informar. ion requested by

_ the staff' describes how the licensee is meeting'the

_ guidance of NUREG 0737.. Therefore, this deferral of the i.

licensee submittal will not alter the implementation of

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plant modifications. Therefore, plant safety is not affected byf this modification in schedule for the.

submittal of information.

I have determined 'that these ccomitments are r'equired in the interest of public health.and safety, and therefore, should be: confirmed by ORDER.

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4 IV.

Accordingly, pursuant to Sections 103,- 1611,1610, and 132 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in

-10 CFR-Parts.2 and "9, IT IS HERE3Y CRDERED EFFECTIVE IMtEDIATELY THAT the if censee shall comply with. the' following conditions:

p The licensee shall satisfy the specific. requirements described in the Attachment to this' Order (as appropriate to the licensee's facility) as early as practicable but no later

- than 30 days af ter the effective date of the.GRDER.

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4-V.

Any. person who has an interest affected by this' 0rder may request a

- hearing within 20 days of the date of publication _of this Order in the-Federal Register.. Any request for a hearing shall be addressed to the Director, Office of Nuclear Reactor Regu'ation, U.S.- Nuclear Regulatory Ccamission, '4ashington, _ D.C.

20555.. A ccpy shall a!sc, be sent to the Executive Legal ~ Directer at the same address.

If a hearing is requested.

by a person other than the licensee, that person shall describe, in-

-- accordance with 10 CFR 2.714(a)(2), the nature; of the person' interest.

and the manner -in which the interest is affected by this Order.- A REQUEST.

-FOR HEARING ShALL NOT ' STAY THE IMltEDIATE EFFECTIVENESS OF THIS ORDER.

If a hearing is requested by the licensee or other pers.as ~who have an 4

interest affected by this Order, the Commission will issue' an Order designating the time and plsce of any such hearing.

I'f:.a hearing is held concerning this Order, the issue to be considered at the hearing shall be whether, on the basis of the information set forth in Sections II and III of this Order, the licensae should comply

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- with the conditions set forth -in Section IV of this Order.

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. This request for information was approved by CMS under clearance number 3150-C065 wnich expires June 30, 1933. Cocnents on' burden and duplication may be directed to'the Office of Management and Budget, Reports Management, Roon 3203, New Executive Office Building, '4ashington, D. C.

This Orcer is effective upon issuance.

OR THE NUCLEAR REGULATORY COMMISSION h

h'u{.' Eisinnut(,[Dir ctor l' h L

Dar e Division of Licensing Office of Nuclear Reacter Regulation Dated at 3ethesd3, Maryland tnis 1Gth day of July 1981 Attachnent:

NUREG-0737 Requirements

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O AITACHMENT NUREG 0737 REQUIREPENTS Impl/Occ Item Title Acolicability Specific Retuirement Subn Jue Dates

!.A.l.1 STA

.aL L (a) Provide STA coverage by 1/1/81 degreed indivi dual s (or equivalent), trained

'to licensee's program.

(b) Submit cescription of 1/1/31 current training procram s.

anc demons trate compliance with 10-30-79 letter.

{c) Submit description of long 1/1/81 term training program.

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Rea:: - 0:erator ALL ment Upgrade [ tion o f and imple-Su:mit descria 3/1f30 Qualification Training Program.

1.C.1 Accident Procedures ALL (a) 5;bmit reanalyses of inade-1/1/81 quate core ecoling and procese guiceli.es 'or ee.ergencj crececures, CR prooose scnedule in: ;ustify delays.

(b] Submit re3nai sis of 1/1/31 j

transients and acciden s for emergen:, Drocedures, 3?.

cre;ose schedule and justify deTajs.

I.C.5 Feetba:'< o f ALL lmplement procedures for 1/1/81 0:erating :x:erTen-a eedback of operating experience (no documentatico subrittal is required).

i.C.6 Correct ?erformance ALL Imple. ment :rocedures to veri'y 1/1/81 or Operating tctivities correct cer' rmance of ::ersting 2ctivities (no documentation submittal is required) w_

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2 Impl/00c Item.

Title

. Acol4caoti f ty Sceci fic -Recuirement-Saba Oue Dates l

11.3.2-Shielding.

ALL (a)' Fave 'available design

.1/1/81 cetails for vital area modifications.

4 (b) Submit technical-1/1/81 deviations to. staff positions.

II.S.3 Ocst-Accident ALL Submit description 1/1/81 Sareling of deviations from staff pcsitions.

II.3.4 Traising to ALL

'a) Have available for '

1/1/81 Mitigate. Core review a training Dama ge program for mitigating core damage (no'documen-tation submittal retuired)

(b)' Implement training

-4/1/81 progran (no documentation submittal required).

II.D.1 Perforhance

'ALL (a) Submit test program 7/1/30 (PWRs?.

Testing of

'(both SER/PWR's).

-10/1/80 (SWRs)

RV/SRV!s (5)' Submit qualification program for PWR's block valve.

1/1/31 (FWRs)-

L II.E.1.2 Aux Feed

.PWRs (a)' Submit-final design and I/1/81 Initiation documentation on. safety and Fl:w grade flow -indication.

(b) Submit final design and 1/1/81 1

docurentation on safety grade flow initiation.

II. E'. 4. 2 Contair. ment ALL (a) Submit d0cumentation 1/1/81

-Isolation justifying minimum contain-ment pressure setpoint for isolation of non-essential penet ra tions.

(b) Submit statement that 1/1/81 carge vatves not ceet'ng CSB 6-e (or interim post-tion)are seale.d and verifi-cation is performed every 31 days.

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em Ti tl e A:clicati:ity 5;eci'ic 07:uireren 3_dlP Oue C3te5 II.F.1

?cs:-Accident ALL a.

.cor noble gas monitor 1/1/31 "onitoring and iodine / par:iculate sampling and analysis submit description and justification for deviations from staf f requirements.

b.

Have available the 1/1/81 final design intor-mation for noDie gas moni tor and iodine /

particulate sarpling and analysis.

II.F.2 Inst, for Inadecuate ALL Submit 3 report detailing the

/1/a1 Care Cooling clanned instrumentation systen for monitoring inadequate core cooling.

!!.X.2.10 Antic. Trip on 35W Submit final design for 1/1/81 LOFW and TT anticipat;ry trio as described in NUREG 0737.

II.K.2.13 Tnerral "e:nanical 35W Submi re:c e: cn e'#ects 1/1/21 Report of H1 Oressure :njectico on vessel in*egrity for

o suum al.h nc.ux Fee daa t er.

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m and ?rebabi'ity ;f failure 3f 0RV/57/R7 I:.K.3.3 SRV/SV 23flures ALL Subri re:ar: :nis:Oric31 1/1/81 5 Challenges and 3nnually :nereafter) of SRV/57 fai!ures and challenges.

I!.K.3.7 PORY Opening 31W Submit re:crt*cn the 1/i/81 Probability probability of a PORV opening during an over-pressuri:a tion transient.

• !.K.3.3 P0 Contro!!er Selected W~

Modi #y the Crosc r'.'o nal 12/1/50 Mcci#ication a ants

ntegral Ceriective ::n.r:Iler (as rec,renced y d).

Acvise NRC wnen -edification is c; male:ed.

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Anti:ica: cry Trip W

Su b.mi : ::n Ta tion a f 1; ' 's; on Turcine Trip Anticipat:ry Trip.

f not curren:1' impienen*ed, submit nodi'ica: ion design and senedule for implementation.

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.imp..i ucc Item Title

.loolicability Specific Re:uirement Sub: Cats II.K.3.13 Separation of SWRs w/HPCI/RCIC Submit results of 1 /1 / 31 HPCI/RCIC eval:ation and proposed Initia: ion Levels;-

. modification as appropriate.

Auto Restart of RCIC

.II.K.3.16 F.e duce Challenges SWR Submit report n actions.

t /1/31 to-RV's planned to reduce RV challenges.-

II.K.3.17.

ECCS syste, 0;tages ALL Submit report on ECCS 1/ 1/31 e.,,.,, =. s =..'

c-~ r~.~ s a

.'..= n a a s

.to reduc 2 outages.

II.X.3.i3 ADS Logic BWR Submit re;0rt of feasibility 4/1 /21 Modifications of A05. system logic changes to

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- II.K.3.21 C55/C CI Restart 5%R Submit report of' evaluation, 1/1 /51 prop; sed modifi:ations and analysis t1 satisfy staff ^

m positi0ns.

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1:.K.3.22 RCIC Suetion SWR w/RCIC Imple er.: pr::edures and 1/1 /81 a.,...,..

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f r HgG '.evel Instruments decurentati:n of :hanges.

II.K.3.23

'Is:lation 5WR w/!Cs Su:mi' ivaluation of I.C.

4/1 / 21 Condens:r perfo rma r.c e.

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II.K.2.44 Fuel Failure BWR Submit evaluiti:n te verify 1/1/31 no fuel failure.

' II.K 3.45 Meaual Depressur-BWR Submit evaluation en other 1/1/31 i:ation than ACS method for depressurization.

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Title AO;licability Speci fic Requirement 3u07 Jue Da tes III.D.3.:

!morc-eed Ir.pl ant ALL Have available means to 1/1/31

odir.e Mcnitoring accurately measure aircorne radiciodine inplant during an accident.

1 I.D.3.4 Control Roca Habitability ALL a.

Submit control room 1/1/31 habitability evaluation in fo nna t io n,

b.

Submit modi fications 1/1/31 necessary to assure CR habitability with a schedule for completion.