ML20003A107

Forwards Response to NRC 801125 Request Re NUREG-0737 Requirements.Consists of Tabulation Addressing Items Scheduled for Completion.Procurement Factors May Impede Schedule.Addl Info Re Emergency Feedwater Sys Items Encl

ML20003A107
Person / Time
Site:	Three Mile Island
Issue date:	01/23/1981
From:	Arnold R METROPOLITAN EDISON CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.C.5, TASK-1.D.1, TASK-2.E.1.1, TASK-2.K.2.09, TASK-2.K.2.10, TASK-2.K.2.11, TASK-2.K.2.13, TASK-2.K.2.16, TASK-TM TLL-680, NUDOCS 8101290593
Download: ML20003A107 (26)

Text

s Metropolitan Edison Company a

e Post Office Box 480 Middletown, Pennsvivania 17057 717 9444 041

, Writer's Dir*ct Dial Numoer Januarv 23, 1981 TLL 68'O g h h Office of ::uclear Reactor Re;ulation T / < !'s'il lvA.

' *-4 ' ' ' -

Atta: D. G. Eisenhut, Director s

-. ." \

Division of Licensing '? J ~ j ~, ', .d[" Q'- ' \l U. S. Nuclear Regulatory Commission 3 Washington, D.C. 20555 iD[fpren /

Dear Sir:

Y ', x gh M 6.d to Three Mile Island Nuclear Station, Unit 1 (~MI-1)

Operating License No. DPR-50 Docket ::o . 50-259 Response to NUREG-0737

References:

1. Letter, dated October 31, 1980, Io All Licensees of Operating Plants and Applicants for Operating Licenses and Holders cf Construction Permits, from D. G. Eisenhut,

Subject:

Post TMI Requirements, NUREG-0737

2. NUREG-0694, "TMI-Related Requirements for New Operating Licenses," Issued June 1980

3. Letter, dated November 25, 19S0 to R. C. Arnold from D. G.

Eisenhut regarding NUREG-0737

4. Order and Notice for Hearing, Docket No. 50-289 August 9, 1979

5. Order, Docket No. 50-289 March 6, 1980, (CLI-80-5)

In references 3 you requested a response to specific reference 1 and 2 items that the NRC staff believes to be applicable to TMI-1. The purpose of this letter is to respond to these recuests. In accordance with reference 1, this letter is filed under oath and affirmation with accompanying affidavit.

Attachment 1 presents a tabulation of TMI-l programs in a format consistent with Enclosure 1 of Reference 1 (NUREG-0737). It includes all 0737 items scheduled to be completed for operating reactors. For each line item that is indicated as being applicable to operating reactors our schedule co==itment is provided in column 3 of Attachment 1. Many of these are given not as a calendar date but as " prior to heat up", " prior to criticality"," prior to operation at greater than 5 percent power". These schedule commitments are based on the assu=ption that the Commission's orders will be modified to allow heat-up before authorization is given to " restart". A separate request for such modifications to 810 129059 N Metrctot tan Ec: son Corrcany is a Vemcer o' tne Generai Pubhc Utmt.es System S:1 P

D. G. Eisenhut TLL 680 the orders will be submitted to the Co==ission. In addition, where helpful for some items, a target schedule to which we are currently working is also provided.

Attachment 1 also identifies where schedule dates have changed from the dates previously supplied to the NRC. The specific scope of TMI-1 programs is described in the text of Licensee's technical references as cited in Column 4. A final column is provided entitled " Comments".

As you will note, Attachment 1 identifies appropriate Licensee technical references related to the NUREG-0737 Enclosure 1 items. The specific content and scope of Licensee's programs is duscussed in detail in these technical references. Virtually all these NUREG-0737 items in Enclosure 1 have been addressed by Licensee at NRC staff request as the original items were issued *.

Licensee has initiated (and in many instances completed) programs and modifica-tions that were responsive to these original items. (NUREC-0737, page viii, paragraph 3, indeed recognizes that Licensees may have proceeded with the implementation of the original requirements prior to receipt of additional NRC clarifications and requirements.), Changes in programs and plant design submitted via the Licensee's Restart Eeper: and correspondence have received NRC staff review and approval (with an intensity and breadta far exceeding other operating reactors). This is acknowledged in the NRC's Restart Safety Evaluation Report (NUREG-0680), and supplements thereto, as well as other NRC correspondence and I & E inspection reports. Thus, we are presuming that NUREG-0737 requirements for restart will be satisfied by the scope and content of the programs initiated (anc in nest instances documented to be acceptable by the NRO staff safety reviews).

For the foregoing reason, Licensee believes that it has already provided the justification (alluded to in Reference 3, page viii, paragraph 3) for any deviations between 0737 and the scope of programs contained in Licensee technical references. (NRC SER's and correspondence, as noted in Attachment 1 address the status of staff concurrence.)

With regard to program completica dates, we have proceeded'on an expedited basis to implement corrective actions and modifications prior to restart where practical, even for NUREG-0737 items beyond references 4 and 5. As noted in the l

j footnotes for Attachment 1, we recognize that procurement and other factors beyond our reasonable control may alter what can be accomplished at TMI-l by dates specified in NUREG-0737. This is especially true for the icng-term items I

whose completion extend into early and mid-1982. Flexibility available to operating reactors for implementation of 0737 items must also be afforded to TMI-1, particularly on items whose schedule dates fall before the TMI-l restart l date.

In the NRR letter of November 25, 1980, the Staff requests that we respond l for TMI-l to appro,ximately 20 items contained in NUREG-0737 and NUREG-0694 which the Staff co4siders to be required for restart. The majority of those items are covered in Attachment 1 and the balance are addressed in Attachment 2

• Licensee can readily identify NUREG-0737 requirements that originated in I & E Bulletins 79-05 A, B, C, NUREC's 0578, 0585, 0600, 0667, 0694, 0565, 0660, as well as the Kemeny Commission Report, Rogovin Report, ACRS reports and generic items, I & E circulars and NRC staff papers or letters that have been issued in the last 1 1/2 years.

D. G. Eisenhut ILL 680 utilizing the same format as Attachnent 1. presents a detailed breakdown of status and schedule for IMI-l emergency feedwater system items. Although this detailed information was not requested by ref erences 1 or 3, it is relevant to items II.E.1.1 and II.E.1.2 for which information was requested, and we believe this display Of the many individual sub-parts and specific requirements for EFW system items is helpful.

We have pursued aggressively correction of many items and the upgrading of our nuclear progra= in many areas in addition to those addressed in the attachments.

We are dedicated to continuing the expeditious pursuit of all of these items.

However, interrelationships between various activities and time required to complete engineering and procurement schedules impose constraints on how quickly some items can be implemented. We believe that safety of operation of TMI-l must be judged by evaluating the status of specific elements within the context of the total nuclear program statua. TMI-l has been and is an operating reactor plant.

In our judgment items which are generic to B&W, or pressurized water reactors, shculd be required for TMI-l consistent with the requirements for other operating reactor plants. We have reflected this position in our commitment dates set forth in the attachments. Nevertheless, our efforts will continue to be directed toward accomplishing all of these items as expeditiously.as we can.

Sincerely. -

-~

i 1 ,'

/ .n v - \;<W--

R. C. Arnold Chief Operating Executive RCA:LNH;jp Enclosures cc: R. W. Reid D. DiIanni H. Silvec

METROPOLITAN EDISON COMPAhT JERSEY CENTRAL POWER & LIGHT COMPAhT AND PENNSYLVANIA ELECTRIC COMPAST THREE MILE ISLAND NUCLEAR STATION, L3IT 1 Onerating License No. DPR-50 Docket No.30-289 This letter is submitted in response to the Nuclear Regulatot,r Cc=missien request concerning NUREG 0737 " Post TMI-Requirements" dated October 31, 1980 for Thre^ Mile Island Nuclear Station, Unit 1. All statements contained in this report have been reviewed and all such statements made and matters set forth therein are true and correct to the best of my knouledge, information and belief.

METROPOLITAN EDISON COMPANY 1

i By / G Gd i L' V //

Chief 0;re' rating Executive Sworn and subscribed to me this 23rd day of Januarv , 1981.

By h- ' '

'~

Notary Public

my L san. :: f '> :

k' -

• Otc , *1.

• h . . - .

^

. .)

Attachment 1 - Het Ed THI-l Response to N11 REC-0737 TI.L-680 Enclosure i requirements items I/23/HI PcgeI ofI7 NRC NUREC-0737 NRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND SCitEDULE in SHORT TITLE SCHEDULE PR0p0 SAL COMMITMENT (3) REFERENCES 1.A.I.1 Shift Technical 1. On Duty 1/1/80 1. Complete R.R. 5.2.2 SER, Sec t ion 2.2.1.b(2) advisor 2. Tech specs 12/15/80 2 4 / t/81 discusses 1.icensee

3. Trained per 1/1/81 3. Complete Compliance. Additional LL CatB STA simulator training

4. Describe L/1/81 4. 3/81 per company program long-term will be completed.

program I.A.I.2 Shift supervisor Delegate non-safety Complete R.R. 5.2.6 SER Supp. 1 Section IVg responsibilities duties 1/1/80 '

discusses Licensee Compliance I.A.1.3 Shift manning 1. Limit 1L/1/80 1. Complete TI.I. 392 10/20/8ii SER Supp. I Section IVe overtime , discusses I.icensee II}

2. Min Shift //l/82 2. 7 /1/81 TLI.- 655 12 /19 / 60 Compliance (See T1.1.-655 f or crew (Target date-betore status of Licensee Procedur c r i t. See comnwni n) in Conduct of Operations)

NRC exams of 100% of operators scheduled Apr/

May 81. Compliance prior to 7/1/82 dependent on personnel retention and outcome of NRC exams.

I.A.2.1 Inunedia t e 1. SRO exper 5/1/80 Complete T1.L- 380 8/8/80 SER Supp. I Section IVd upgrading of R0 2. SR0s be Ros 12/1/80 discuanes 1.icensee and SRO training 1 yr Compliance and qualifications 3. Three mo 8/1/80 trng on shift

4. Modify 8/1/80 training

5. Facility 5/1/80 cert i ficat ion

___.~ __ _ _ . - _ _ _ _ _ _ _ _ . . _ . _ _ _ . _ . _ . _~- . _ . _

I.A.2.3 Administration of Instructors 8/l/80 Comp l e t e TI.I.-380 8/8/80 SI:R Supp. I Section IVe training programs complete disciasses 1.icensee con

A t t actisment 1 - Het Eil THI-l Response to NUREG-0737 TI.I.- 680 Enclosure I requirements itema 1/23/81 l'egelauf 17 NRC NUREG-0737 NRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM HUMBER ITEM AND StilEI)lli.E TEGINICAL

, 6 SHORT TITLE SCHEDULE PROPOSAL COMMITHENT(3) REFERENCES 1.A.3.1 Revise scope and 1. Inc. scope 5/1/80 1. Complete TI.I.-488 10/3/80 He t erenced TI.I. requesteil criteria lor 2. Inc. pass- $/1/80 2. Complete T1.1.-286 6/30/80 NRC to actiedule exams licensing exams ing grade SER Supp. I SectIon IVF

3. Simulator 10/1/31 3. 10/1/31 .IIscusees I.leensee exams Compi1.ince I

Attachment 1 - Het Ed THI-l Response to NUREC-0737 TI.I.-680 Enclosure 1 requirements items 1/23/81 Page2 of 17 NRC NUREG-0737 NRC SPECIFIC LICEN:ll 1: 1.ICENSEE C09 TENTS ITEM NUMBER ITEM AND SCilEDill E TECilNICAL

& SHORT TITLE SCHEDULE PROPOSAL COMMITr.ENT (3) REFERENCES I.C.1 Short-term accident 1. SB 1.0CA 6/1/80 1. Con p l e t e . R.R. 3.1, 10.4 See conunent under and procedures 2. Inadequate 2. Cowl.lete. g1L-235 6/30/80 Licensee Schetale t review core cooling Conun i t men t s ,

a. Reanalyze 1/1/81 ASLB Testimony Licensee letter referencing and propose of Broughton, ANO-1 ATOC guidelines that gu idel ines et al. satisfy 3a will be submittes-

h. Revise First 2/15/81.

proce- refueling 12/16/80 NRC dures outage and B6W owners afLer meetlug 1/1/82

3. Transients &

accidents

a. Reanalyze 1/1/81 3a. :e neric ATOG 156U and propose guideIines for ANO-I guidelines submitted to NRC for

b. Revise First review. 3h. Plant specific ATOG proce- refueling 3b. First refueling program is currently dures outage after 1/1/82 scheduled for 9/81 implemen-after tation of procedures &

1/1/82 operator training.

I.C.2 Shift & relief Implement 1/1/80 Complete R.R. 3.1.2 SER @ 2.2.lc & SER turnover procedures shift turn- Supp1,IVi discusses over checklist Licensee compliance I.C.3 Shift-supervisor Clearly 1/1/80 complete R.R. 5.2.6, SER 0 2.2.la & Supp. 1 Ivi responsibility define Supp. 1, discusses Licensee superv & oper Part 2, Q25 Comptlance responsibi1itles I.C.4 Control-room access Establish 1/1/80 Complete f R.R. 4.0, SER 0 2.2.2a discusses authority, f10.3.3, 10.3.4 Licensee Compliance limit access I.C.5 Feedback of operating Licensee to 1/1/81 3/1/81 { TI.L-39 2 10/20/80 SER Supp. 1. Section IVk experience implement i discusses 1.icensee Complianc procedures l.ic. Procedure EP-030

[ implemented 12/22/80.

. Ap-1032 under review.

I r , i... 7/qIn1.

Attachnent 1 - Het Ed THI-I Response to NilHEG-0737 TLI.-68'O ,

Enclosure 1 requirements items ~~ 1/23/81 Page3 ofl7 NRC NUREG-0737 NRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND SCllEDUI.E TECHNICAI.

t b)

& Sil0RT TITLE SCllEDUI.E PROPOSAL COMMITHENT REFERENCl:S I.C.6 Verify correct Revise 1/1/81 Complete R.R. 3.1; Supp. 1 Scope of program as defined performance of performance Part 1, Q'2 3,54, in R.R. SER H C2-7 dis-operating activites procedures 58,60; Supp. 1, eusses Licensee compliance.

Part 2, Q21 & 22 See also item II.K.l.10 I.D.1 Control-room Preliminary TliD Licensee s<lmdule T1.1.-346 7/14/80 NUDEG-0/52 documents design reviews assessment and is identificil in TI.L-559 11/7/80 Nt:C evaluation of TH1-1 schedule for I.l L-019 da t . =.1 Heport on THI-l control Room.

correcting 1/21/81. C.R. Iluman Fac t ora deficiencies review, Dec., 1980 I.D.2 Plant-safety- 1. Decription TilD 1. TilD None Licensee will review NRC paramenter display 2. Installed TiiD 2. T!!D documentation (NUREC 0696) console 3. Fully T15D 3. TBD when available implemented ._ _ ._ _ . _ _ . ..

7_.

II.B.1 Reactor-coolant- 1. Design 7/1/81 1. 7/15/81 , R.R. 2.1. .! . 2 SER, page C8-60 system vents vents discusses Licensee

2. Install 7/1/82 2. 7/1/82( ) Comptlance.

vents 3. Procedure development (1.L Cat B) 3. TBD lunderway as generic liW

3. Procedures 7/1/81 (See Comments) _ _ d ictivity.

II.B.2 Plant shielding 1. Review 1/1/80 1. Complete (See R.R. 2.1.2.3, ,SER @ 2.1.6b notes status as designs Comments) 7.I iof 7/80, R.R. amendment 22 revised schedule.

1. Initial design review has

,been completed. Further ianalysis refinement is

, scheduled for completion by 6/30/81 and is supporting

, modification finalization.

2. Plant 1/1/82 2. lut outage thru Yl.L-500 ; 10/2/80 2. 7/81 is optimistic date modifications (First 7/82 (See conmient .) for MCC 1A/B shield wall.

outage thru 7/82) ,

(LI. Cat B)

3. Equipment 6/30/82 3. 6/30/82 qualification

t s e .

a l - r. t e -

1 s o 1 i e r l m - f 0 e bo a a. ua ,

o 8l

- l u i V p l

t t t

m d r s - ss / b f t t eg 2 id ng ml np t 01 o a I ol d st oo gh o n ea / s e 8 84 6/

t s

on ci nCiet ipl l nc r e --- sset o e1 oa pb 0 ss6 .

- l a d y o wt r /ue i spen m t

. s 2' g sgf l t i e ea1 v w bi e -

uc e gn L. / a I enol i tcseap ml m/t e ed icnil I r cnnsf saonot no T 1P t i od t l l

ul i en rmg1 e S e gon 0nd

.d . e varl R C

eiN g n

. i D. u q

~iiie dl t ceet se ec nun b c o cih nl r enw pe e - ci a c6 ac mop l er a ,i r n2 et osI r i I amaI p c i. n l d i LP &i p s. soc nt s 3 o e r t t s

8. net i gcc a cC od an snu a .em ic o e7 l a .s . d r ei t siid r3 a 1 R t n eoieo 1

,de y e o i mml pe aet b sr emPi tated7 d0 o n

.eN t

S . eg ps2 p l

2 e d p st i et T 20l R n us ot ait s aE mt a - i s nsi et r p N 8 w i

- 0 n . oe pum E e/o el S u .l nl u nr i Gt e0 pr1 p oc u l

H 7 nd p e gh om1 Ei H R k am c eeeieul c .

R scvt at i i t f b8Rd nu/Ul .

! c8 sr8 m Ei/ eo/o nr s os O Ef c r a Ei Sd ad eal nexvan i. r i pwisl N a i .

. SL7 r c5 c opa C S oags i i

1

,; :1 i*

0 0 8 0 .

8

/ 8 /

, 2 / .

8 - 2 4 /

0 /

0 2 . 2.0/1 S 2 1 3 1 LE 1 1

EAC 1  ;

0

.ft ECN . 0 6 SI E 2 0 1 1 . 2 O NNR El El 55 5

. . .S-7 CCF I R. . R. LL 3 I EE R. 3.iL. L R - R T 7 LTR t 1 l T y , Il?

0 nd y C n n oe - it E o o i t ) )

R H - H - t e s s l U

N t t n eg t 2 g

n ag t r) t n

t n -. ica nei n8 i na . e e o s y el l e l et1 m m

. t t

m e ( mpp nmm m/ 1 p

m m

ul /

8 m o1 o m s t

. r i

e t T i oa i n/ a ca0 1 C8C n c i 1 s N aCS a S ot 3 8 / e n E Dt/ / e1 e m e 1 El E.E u t - t o H n gS nu S ( i1 1 e/e m r 8 p t l onC1 on C1 l m /S0S o o /

s e

n e EiT rEH D1 CiR1 Ci r /

1 r

R8

/

Bb r 4( 1 (

/uo C f e /

1 R m CliH o .1 .o .1 2 sf . . e 4 e I CO at b/ at b/ . a h c B.

l r LSC l I l 52i 2 5 1 2 2 S

. 1 2 i

- u , a i1 ' I Il l ,

j, I

H q-e .

0 T r 1 1 2 .

8 d 1 1 8 0 1 8 8 . 0 /

I 0 2 8/ 8 8 / / 8 5 E 8 8 8

/

/ /1 / / 1 1 1 t e / /

1 1 / 1 g 1 / / . 1 /

e r 1 1 .

u l

/ / / / 0 / n / 0 7 / f n2 H s A 1 1 s 1 41 1 i 7 1 - 1 oo1 S n t . i o O e s e c e st

- o l

P l t e) t g i v - nis c i ) -

1 n C O t B t ae t B enf t l -

osc E

I R a g n i l l it i r a i oe t F P m ct pnmemt p mVt pt ncovgl l t pp n I m i a oiamaim t aS amsaep - n t a s e CDE i r et f C l nr erno i r C oel peki acce m ENL et ni eigl gI C m g& Ct P sr ct t eivh h PAU t sadL vaopo b o L. os srdl c c S D n yl oL err mr . . urVI . . l e ninae r HE I sP m( Dt pI pab S pR( a h Bt I di vT t CFl l t RTC . . . . . . . . . .

A NI S 1 2 1 2 1 2 3

. 1 2 i

e y

r t n o e o t rc f s . i

_ n o a t . t e f g st n i n d n se so i g gi & em oi nt t e pt cn i ae f r . a 7 ci ngg ec al eei 3 E t p ii a i vu vi 7 L - l d 0RT sm at m ria l l q eae - au

_ - EI oa Tmd R vr Vl _

CBT P s EM _

RUT -

- UNR 4 N O 3 1 3 -

HH .

CES B. B.

RT I I D. D.

NI& I I I I I I

Tl1.-680 Attachment 1 - Het Ei! THI-I Hespontic to NilHEG-0/l/

~~~EncIusure I reviu i rement s items Pagej ofj]

NHC Nt! REG-0737 NHC SPECIFIC I.ICENSEE I.lCENSEE COMMENTS ITEM NilHBER ITEM AND SCilEDill.E TECllNICAl.

& Sil0RT TITI.E SCllEDllt.E pkOp0 sal. COHHITH1'NT . HEl'ERENCES

-.. , _ . . - . . . _s . - -

I II.E.1.1 Auxiliary feedwater 1. Short term 7/1/til *

1. Complete IH.H. 2.1.1./ See At tachment 3 for j system evaluation 2. l.ong term 1/1/82 i 2. See Attathment 3 I urheilule 6 modificat ton f o r- Items l status l II.E.1.2 Auxiliary feedwater 1. Initiation See Attachment 3 See Attachment i See Attachment 3 system initlation a. Control 6/1/80 I

& flow grade

h. Safety 7/1/81 grade

2. Flow ludication

a. Control 1/1/80 Krade

b. 1.1. A tech 12/15/80 specs

c. Safety 7/1/tli d

grade -- ---

' ' ~ * ' ~ ~ ~ '- ~~

II.E.3.1 Emergency power 1. tipgrade 1/1/80 1. lietore cu lt icallt) R . It . 2.1.1.3, SEH 0 2.1.1 discusses for pressurizer power supply j (Targeted 7/81) I I . 2. 'l I.icensee compliance heaters 2. Tech specs 12/15/110 2 . 4 / 1 / 11 1 II.E.4.1 Dedicated hydrogen 1. Deuign 1/1/80 1. Complete H.R. 2.1.I.4 I.icensee will' install penetrations 2. Install 7/1/81 2. Helore cr it icalit y 11.2.4 dedicated recombiner. pro-(8/111 taiget datel cure:wat cont rolling schedule ll.E.4.2 Containment 1-4. Imp. 1/1/80 1-4. 15efore c rit. R.R. 2.1.1.5 1-4. SER 0 pagen C2-6 luolation diverse Isolation ,

except per connent s. R.R. 11.2.5 and Cil-21 addreuses status dependability 5. Cntmt preasure (7/81 target date) Asl.it Teutimony of of I.icensee Compliance au setpoint 5. Complete. I. 1.anene, 12/4/80 of 7/111. NRC letter dated

a. Specify 1/1/81 . T1.1.-229 5/9/80 1 1 / 5 /110 discusses i pressure acceptability of 1.icensee's,

b. Modif1- 7/I /lil purge vaIve design and cations operatlon.

6. Cntmt purge 1/ I /fli 6. 4/1/lil Heilundant utgnal f ar RCp valven Services

7. Radiation 7/1/81 - 7 7/1/fil (l. i n e lireak Det ect ion) utgnal on ,

(2/111 t arp.et. dat e ) j dependent on late ' til purge vaIven j ' delivery of qua1ifled erluip-

8. Tech specs 12/15/110 t  !! . 4/1/81 ment. Const/ completion date

! THit

s d e dl d C -

y f I

. h2 o .

t 8 rl ei el g

at n eb eco r pt di a

/

T i

f i

0 1 o L m e/ ngxa ra p e . r 8 8 r m1 .rd a

& e n el ov i oel

_ 6/

. 3 e l sl e t em1

/

&l t a u o l a ul gubf e cd c 1 2 g b el ni .

e' . 3 ocn e ri - nt i t 1 1 / a 8 sa gorl anes uo ,

iv7 s .e T1 P 1 en

.r o s nf ei oet t

>nn eamnqne r J ei e a

d1 a .

,n1 t a ni pr7 e up3r o3 s 1 2 e

.s n 2d l l i u r sa8J2 el t p k g c

d eue - er/

saos d g f e t cd t g3 : nxm c.f at or o ni n r m i n oye

,d r aoaea el rrt d y yei

. oeo C It p i oL e

oB pe ,d t s d pG e t bt t s 2 on t oa t sc S

i t yei t

3, t l i u r e l ye - acee 8 il c en T cr e ot nl p rf rd ese esa N eosI 2, on caeb eoomea g nr e

.S ss /t t 1 uan S si E

M S gn 1 i pl i pet ci r o v s_E ,unc-se

/ouo 1 dl i

,c p ul M Rt e c e F. st l ummn l r

.dR R sm O rdil l oios ct Cidle o _6 o S d 1 rEi l. .aat Ei o 1 reva K. m SdC C E SC1 I a i. I oori t.

i F mcv u 1 E (

iIi 8 O f 1 S 1 - o 8 .

1 l 0 0 0 / l t

a ,

8 ,

8 8 yl 1 , i B.

1 l i.

s ) B. f t s)

I 1

/

21

/

2

, f6 2 na2o /

1 T, 3 I

. seg S oeee . 1 56 .

v 2. 8 01 2. 8 /. / 0 S S e / mt1 9 1

2. A ny mA ynno g 1 1 LE A g 0 .

i e pQ2 .

ny

2. 8 a

1 t EAC 0 an1 0 anl 0 noab1 . 1 . 1 s ,01 p 1 ECN 8R o . 8R oA8 ot R a . 1 0 .1 01 0 2 en88 . u ,I .

SI E S2I 2 NNR / m2/ m(/ mh ( 2 1 0 21 0 .1 0 t : //

4 5 .i 5 .i 5i g . 5 5 215 7

El iE CCF 1 t t . 1 t t 1 t ut . . .

B. a1 t 52 2 . t . .

R. ra R.

I 0 s s R.0ne/ s s R. /0 sero nBI s R. R. . R.

/ e// R.

L. R. R. S K91 I

3 I EE I. I.

7 LTR ne- I I RA RPR R 0 1 I TR1 I TR1 i RR T R T R T y)

C t e E it

) ) ) - l a s H e e e li ) ) aD e N

t a

t a

t a u s s c cs s d t t t i t nt o m ) d d a n n t e g

en ,

e 3 c e en e i r e t

t ( c i

c

) I

) n u u n r r em e e i T i

t y n n n C a f m t s N I

(

t s (

s (

1 t s ( o o o T e o e n s E 2 2 i 2 i 2C 2C 2C e 1 RC l 1

8 ot E EI E. H i

q 8 8 r18 p pn 81 m 81 m 81 m '. e / e /e o8/ ed /

SUT /8i / 8i / 8i en m

.1 e 1

se NDI 1 /t 1/ t 1 /t 1 e

/ S 1 e

/S f/1 e8/ S a o /

e m EEM /8 p / 8 p /3 p1 - / S C 4 R e i

1 t 1( 1( l (4 CiMl 1( o 1( o 1( o' r I CO . ,, . .

I i LSC . . . . . . . . 1 2

- u 1 2 3 4m 5 6 1 2 1 I q H e T r 0 0 8 8 d I -

2 2 2 2 2 2 0 / 2 0 /

E 8 8 8 8 8 8 5 8 8 5 e 8 / / / 1 / / 1

/ / / /

t r 1 1 1 1 1 / 1 1 /

e u L 1

/ /

1

/ / / / / 2 / / 2 H s A 1 1 1 1 1 1 1 1 1 s1 o S 1 e

- l O e tl t s c c p e ne n ) t) or s 1 n C 0 s

t a g ev e cA nB t uc E I R a l g - n - eme mn e e oe t F P gr n ar n r nl ne l pt l mt esp n / un s I

o eci i r o i ui i g o sal ua d

e. CDE nil a - t a sar ao or C al rC ag u ENL et t r ceh t et rrh h PAU l i i t p t thi t t st e gec c S D b n d rm nngn nnent nd oy bt c nenLL. svsL pme

- a ME oo oaa oeio oeroa Ch uee1 S mT( I l i( U eT

_ t CEl l Nm I ps C mhm C m pC w t RTC . . . . . . . . .

_ A NI S 1

2 3 4 5 6 1 2 3 1 2

_ ss g r er n o rf vo i

f oel t

- f i aa

- r n e l vc o o r se i t

- i o erkd i

n t f c i cn o ao l roi m

t e pel pzbl nnt

- eoa ui e t

n miug sr ,v 7 e ut qn use

_ rcei rsel 3 E d t edl esv 7 L i st ao wel d 0RT c neno oran

- EI c I di c P pva CBT A EM RUT UNR 2 N O 1 1 Ml i .

CES F.

RT F. I C.

NI & I I I I I

- * .4 . i

At t aciunen t 1 - Het Eil THI-l Response t o EllHEC-0/31 Ti.l.-680 Enclosure 1 requirements items 1/23/81

)* cage 7 of 17 NRC NUREC-0737 NRC SPECIFIC LICENSEE LICENSEE C(MIEtn S ITEM HUMBER ITEM AND SCllEDllt.E TECHNICAL

& SHORT TITLE SCllEDULE PROPOSAL COMM11HENT REFERENCES II.K.l.1 Review THI-2 PNs Complete R.R. Supp. 1 SER discusses I.icensee and detailed Part 1, Q29 Compliance @ P.C2-2 claronology of the )ctter, 6/28/79 TM1-2 accident.

II.K.1.2 Review transients Complete R.R. 10.3.1; SER discusses 1.icensee similiar to Supp. I Part 1, Compilance tl P.C2-2 THI-2 that have Q34 thru C2-4 I

occurred at other facilities and NRC evalu- i ation of Davis-Besse transient.

11.K.1.3 Review operating Complete R.R. 3.1.1; SER discusses 1.icensee procedures for Supp. 1, Part 1, compliance O P.C2-4 recognizing, Q32 6 50 preventing, &

mitigating void .

l formation in l '

transients and accidents. _ . _ _ _ . . . _ _ . . . .

II.K.l.4 Review operating Complete R.R. 3.1.1, 6.2, SER discusses I.icensee procedures & Supp. 1, Past i, Compliance t8 P.C2-4 training Q 32 6 52 instruction.

• i e

9 4

L i 1

g e egd c ne f v - nis 0 , o e I r a ni e e 8 3 67

. 3 ge e .ht s 5 n- t as eie i r unnv t t r s

e n6 s

e n6 I. 7 g e 2 wt snn 0 e-

• e -

I 7 a s uior1 c2 T3 i c C. eioaco c22 l'

L P t nim l

i. C.4 1

i. C.

1 P P s O leirmad r ed . .

e s pd V nar e K. se @E. eO s ma a aI s l s se o uc c toscr.eee spi s el s e cn uc uc S r o cno c n T

N sa s i i i d oad l nup s l

sa s i i l ii s a E dl r rl ee a M p mat l cb dl pa dl p

M R m egnio e Rme R m O

C E

SC ot eoer I r c v pto; c E

So e E o S C i

ijC '  ! '

'  : I '  :!

0

• I 2 8 ,

4 2 / I 1

5 9 ,

p6 1

,p3 u1 2

, p / 5. rat 2 S 2 p5 S2 1 1

P LE u4 4 1

, 1 EAC 1

.S  ;  ;

.1 .

ECN 3 ,1

,0 ,5 2 8 3 SI E 62 5 )

NNR EliE 3

. rt L t 6 .p -

2 7

3 CCF I EE R. 1 . a P, r

a L I

R. u2 p1 R.'sl .

R3 P S P r RSQ R 7 LTR

. 0  !

C

_ W l

u lf t

o t

g g 2 e I T 4 s N -

e n

• EEE e E t o t ELH t e

p n Sl T l

e I l

s e NDI l p I p e m EEM m R e Cl M m e r

l o o

l. CO e C I i 1 SC C S

- n I n H e -

T r d 1 E

e t r e u l M s A .

o S

- l O c P 1 n C O E I R t F P n I e CDE m ENL h PAU c S D a ME t CEi t t RTC A NI S l

s s e 8 n d dl r r , o e l sgnod ueg V-t ti r e u nnare - d pn l . n nt u t - . vso oi t t neoi A nne ea sl o l I il c .

i nsnaicr n , iom' mi sl n o S t o w t ot ol aopod t nt Aa yoyc irt o e l i i ncemr r i e aet ie~ r ii an ot ct if it o st arln oniof v l st e pet r h rii t asu .o f d e f rl a pot l aoime d r ci oq t i n d s t aoimn c a psevl neunu ssle V-v . w oril ac suq yspe . onnenas i b oo sat i t

nneiA n e e pi t a nsf e f e R w coaroi

- d oiv ui t aa r i vn o i uit eeput eovm yeivl d qsd sn F rl eel wt nd t d r aaa mil ot 7 t t t eaneoneeoSf eapee eageasauc i et ar a 3 E eaiR varpat t t Ei V voSb il i cl ert nt l ivp e 7 L f l s vosoongagoi ps mf 0RT aeo . . eser sieenpn Rid pildf I ui monoe I pocd

- EI S r pa b GBT EM 6 7 RUT 5 UNR 1 l N 0 1 Mi i CES K. K.

RT K. l l

NI & 1 i l 1

1

Attachment 1 - Het Ed THI-I Response to NURFG-073/ TI.I.- 680 Enclosure 1 requirements items 1/23/81 l' age 9 of 17 ,

NRC NUREC-0737 NRC SPECIFIC t.ICENSEE LICENSEE COMMENTS ITEM NUMBER ITFM AND SCilEDUI.E g3) TECIINICAL

& SilORT TITLE SCilEDULE l'ROPOSAL COMMITMENT REFERENCES II.K.1.8 Immediately implement 4/1/81 R.R. 11.2.l; SEli discusses Licensee procedures that (See Comments) Supp. 1, Part 2 Compliance @ P.C2-6 assure two independent yll Revised Tech Spec will be 100% AlV flow paths sulan i t t ed by 4/1/81.

or specify explicitly LCO with reduced AFW capacity. -

. . . . . . _ . .....m.m II.K.1.9 Review procedures See ll.E.4.2 R.R. 2.1.1.5.3, to assure that Supp. 1 Part i See also II.E.4.2 radioactive 11gulds SER discusses 1.icensee

' 459 Compliance @ P.C2-7, and gases are not transferred out of containment inadver-tently especially upon ESF reset). i I

List all applicable systems and interlocks.

. - -- ;- . a. -. . - - . _ . - - .. - - . . . .

II.K.1.10 Review and modify R.R. 3.1.3, SER discusses, Liccusee Complete (as required) (See Comments) Supp. 1, Part I, Compliance @ P.C2-/

procedures for Q30 item is complete with removing safety- jTI.L-655, 12/13/80 regard to administrative related systems j controls. Various from service (and '

surveillance & maintenance restoring to procedures are coutinning a service) to assure to be prepared or revised, operability status is known.

i

! 8 i

0

. l

i .  ;! ll!

1 7 d .

1 um eg i I t r e t n 0 f e h t ei e wes 8

3 o e e et i e l t e p HO e e e ps f

I.

>./l Mge s

n8 e-s nH e-s4l n1 a e- u s

n9 ot e- c me sl nI e-c2 iV rR t O I c2 P T /a c2d c2 .

c2 i e

1 P i

. C. ec L C. r&

I P i. C.

I i. C. vi I i. C. b l

i r

s P u .

s e@ sP s Pi d ,P l C ee ssd ,l.

s e s e eon s eOl s i .

s se ees s e s e s e i

se uc rpev ri uc uc ucn uc wt a c n S c n sa c n cnis cn gN sa r we or T sa sa n sa n i i dl pt ol i i N i i i i d o i i i g E dl p dl dl ni dl pii nn t t

p pat t m a r n 9 R m R m Rm c t

m ar l E

i SC o Rbeeo t t 0 E o _E o E o r u C SC E o6 e p SCTd

,S C SC1 s

_ 1 1 1

2. I I

i

, f t t 1 ut ,ra , r 1 1 or 1 a 6 - t a 2 P . r

.S E pQ .1 t P

2. 2 ,

I EAC p l . c 8 1

. I 1

l. eI 5 ECN SI E S1 u,

C e S

1

.I 1 H NNR .t . l . p .p . ,p EiE l r .R p8 p5 p0 7

1 CCF R. a R. b a . u1 R. u5 R. 1 . u3 I EE RSQ R U S )t 7 LTR RP HT H S ')t 0 )

1

(

y E t 8

H i

/

l I l

iN /

s~ a m c )s p )s 5 t

oe t

)

3

(

i t t u

t t e i n a nt e

i T r en e ea s N md n s e C un H E e m E E. E t

oi e o t

io n l

I i t

e e 1 e Ce je SUT l 8 rC r g s e n NDI l p p / o e o er e e EEM f e ea 1 f e Se R r Cl Ml m m /

i l. CO o

C o

4 i B ST ((

1 u 1 SC C t

(

- q l

l e i r T

I d

• E e t

r e u s l H o A l

S

- c O P

1 n~ C O E- I R t F P n I e C D E.

e ENI h PAU c S D a ME t CEl l t RTC A NI S l

d e os , s l d - e-g f nh t e - g s sr a na co n oat s s a , l nf m eo r aci ut i npa ct a ioe r t d u d u t eesf ouh i n c t t ua nt nf nea V

acr soi p f ess i cni d r aa gi or r

eanae wnscny -

t g 2 i mun nneo h ol in .

eef cpog n id sod ooO n f R t eoo ngn pnaseail I or ul cif t i d r

oo emet s d Pi oet uc d rH nint et eat e sino d .

l onsaaT . uia _. Tart er pndhil ea) oR nt neieuee rqt c . c nl i i osnt erb soZ on l

l i nr uol aaneqe en t

nh e or one.sf emuq uenil._eisel u pahii a ort l al l

id s u( ihPi e si t i mosennit cun.oigeB e l t ebt u r e s yl cas soe d h 7

3 E e s i n u m n .. o e a apcnl r e manc ccnl eiun t i r sooak t t a 7 L kd r enrkd ,c eod n pl vd 0RT . r ph ml s ennsai eri niacr

- EI GBT a neh oranf c Hapt cet aoa ninoh.PS OL acc .

ciaa D aoemc D pt al mat EM 1 8 9

_ 3

. 1 RUT 1 2

- 1 1

UNR . 1 .

N Mt Oi 1

. l l

5 I CES . .

K. K.

RT K. -.

NI & I K. K. 1 I I

l i 1 I

l l

, i! 1!!  ; ,i ; ,i l I j

) , i , ,

A t t acliment 1 - Het Ed TM1-1 1:esponse to MulqG-0737 TLL-680 Enclosure I requirements items 1/23/H1 Vagel?of 17 NRC NUREC-0737 NRC SPECIFIC 1.lCENSEE I.ICENSEE COttlEN TS ITEM NUMBER ITEM AND SCilEI)ULE (3) TECIINICAL

& SHORT TITLE SCllEDULE PROPOSAL. COMMITMENT REFERENCES I

II.K.1.27 Provide analyses Complete TI.I.-285; 6/30/80 See iten. I.C.1 for long and develop guidelines R.R. 3.1.1, term items and SER 0 and procedures for 6.0, 8.I l' . C 2- 18 inadequate core cool-Ing conditions. Also define RCP restart criteria.

II.K.l.28 Provide design tinat See Item II.K.3.5 See item See i t e[n I I .K. 3.5 and will assure automatic 11.K.3.5 SER at P.C2-18 RCP trip for all ,

circumstances where required.

11.K.2 Orders on H&W 8. Upgrade /_IN See See 11.E.1.1 See ll.E.1.1 See ll.E.1.1 plants system II.E.1.1

9. FEMA on 3/17/79 Complete R.It. Supp. 1, SER 9 DI-1,2. IOIEA complete.

ICS (See Coimnents and Part 3. 012 (ontinuing program to references) TI.I.-285 6/10/80 i moili f y syst ems ~

10. Safety- 7/1/81 See ll.K.l.21 See II.K.I.21 See II.K.I.21 grade trip

11. Operator Complete Complete R.R. Sect t on 6 SER 0 C2-9 training, drilling _ . _ - , -

,I.lcensee is evaluating B&W

13. ~1nes al- 1/1/81 473fgg(1) meclianical icport and will submit report t Information to NRC at

' conclusion of evaluation.

i I

t i

TI.L-680 Attachment 1 - Het Ed THI-l Hesponse to NtlHEC-0737 1/23/81 -

Enclosure I requirements items Page Llof_11 NRC NUREC-0737 HRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND SCllEDilLE - TECHNICAL

& SHORT TITLE SCllEDULE PROPOSAL COMMIT"ENT (3) REFERENCES II.K.2 Orders on B&W 14. LLft See See l l .K. 3.2 See ti.K.3.2 See ll.K.3.2 plants (cont) frequency ll.K.3.7 of PORVs &

SVs _ .. .

15. Effects of Complete Complete TLL-285 6/30/80 .tSt.H prefiled test. of slug flow :apra indicated NRC action on OTSG i cap.i red

16. HCP' seal - Complete ~, Complete TLL-285 6/30/80 NRC actton to review damage _

17. Voiding in Complete Complete _ _ , , _ _ . ASLB prefiled NRC RCS . testimony of D. Ross indicates Staff Actton

_ _ .. i , . .

' Re<t r .

_19. Benchmark Co.aplete Complete . TLL--285 6/30/80 See Itein ll.K.2.17 analysis of Comment seq. AFW fl.

20. System Complete i Complete TI.I.-285 6/30/80 See Item II.K.2.17 response to lConnent SB LOCA j II.K.3 Final recommenda- 1. Auto PORV TI.I.- 392 10/20/80 isolation l lPerreference, engineering is dependent upon tions, B&O task force a. Design 7/1/81 la. TBD (See Comnent(s) 1 I1.K.3.2 (0565) b. Test / Ist refuel ,3b. TBD (See Comnenta) install 6 mo.after:  ;

statf approval iLicensee will provide

~

2. Report on 1/1/81 g , gg 3 PORV failures status report and scheddle by 2/81 E Rei?oftliig~~ '~1/1/81 Complete Tif-392 10/20/80 !ASI.B testimony of Hoss/

SV & kV j 'TI.L-028 1/18/80 !C apra discusses 1.icensee failures &

• l Compilance i

• cha11enges I

! i  !

i ii i

. I i

TI.I.-6HO Attachment 1 - Het Ed THI-I Response to NUREC-0737 gf23fgg Enclosure I reiluirements items Peg 2 Eof _H NRC NUREC-0737 NRC SPECIFIC l.lCENSEE 1.ICENSEE COMMENTS ITEM NUMBER ITEM AND SCHEDUI.E TECHNICAL

& SHORT TITLE SCHEDULE PROPOSAL COHNITHENT (3) REFERENCES i

a tier at P.C2-18 discusses ll.K.3 Final recommenda- 5. Auto trip of I.icensee Compliance Lions, H60 RCPs gg)

I task force (cont) a. Propose 7/1/31 Sa. ThD R.R. 2.1.2.5; All engineerinn L (0565) modiilea- hpp. 1, Part 1, procurement coneingent Lions Qll upon I.Ol'T I.1-6 t est result '

b. !Iodify 1/1/32 513. THD T1.1.-192 10/ 20/ttu predictlon. 1.icensee is B6W letter of partlelpaslug in generic 12/4/80 Taylor to 117.11 ac t t v i t y on t h i s item.

J11113 p _ Chec k) .

7. Eval. of 1/1/31 l1. A . per ASI.ll- See l l .K. l.2 Seu it.K.3.2 PORV opening ilRC 't. 1:oss i probabi1ity Iestimany (11..C.l.2)

17. ECC system 1 / 1 / 13 1 rBD TI.I.,J9 2 181/ 20/;t0 1.ieensee rergues t ed ontages 4 (see ...mments & clarification in referenceal

, ^

t refeience) T I.I. . Licensee received verlial clarification 1/19/81. Evaluatton of

-~"~ ^ - - ' '- - - -

scope 6 schedule underway.<

4 j Status Report wit h schedult to be provided separately ,

by 4/1/81. l 4

30. SH 1.0CA -

I&in See i 1. I' . I 31 See !I K 3 Il methads

, ;ee I i .K.3. ll

a. Sched. 11/15/80 i

' outilue

b. Model 1/l/82 I

c. New 1/1/82 analyses or 1 yr after stali approval J-131.%:ompi t ance 1/1/8 l ritu TI.I.- 19 2 10/20/210 See Hetetence wi t ti Cl'R or 1 yr Ifnde s evaluation -

g 50.46 after  :;ee 1:elerence

- stalf approval

Attacliment 1 - Het Ed "IHI-l Response to Nt! REG-0737 TI.I.-680 Enclosure 1 reilui remen t e, items 1/23/81.

< PagstSofI7

. NRC NUMEG-0737 NRC SPECIFIC LICENSEE LICENSEE COMMENfS ITEM NUMBER ITEM AND SCllEDtil.E TECHNICAL di SHORT TITLE SCHEDULE PROPOSAL. COMMITHENT (3) REFERENCES i

l II.K.3 Final recommendations, 40. RCP seal See See 1 1. t; . 2.16 See ll.K.2.16 See 11.l;.2.16 l

1150 task force (cont) damage I1.l;.2.16

43. Effects of See See ll.K.2.15 6ee 11.l*.2.15 See 11.l;.2.15

slug flow II.K.2.15 Ill.A.1.1 Emergency Short-term Complete Complete it.R. Sec t ion 4 SER, Section C3 discusses preparedness, improvements 1.icensee compliance j short team .

III.A.I.2 Upgrade emergency 1. Interim TSC Complete 'l. Comples. R . II . 10. l.1 & 4.0 1. l'acilitics luration I

unpport facilities OSC 6 EOF filent f l ied ; conanonica-tions Installed anil utilized in drills 2& 't. Scope and athedule

2. Design Tiln 2. Titu

3. HodifIca- TILD 1. T!!D evaiuation await Lions tercipt & evaluatton at NUREC-0696 Ill.A.2 Emergency 1. Ilpgrade 4/1/81 1, 4/j/gl R.R. Section 4.0 1. Iml.lementat ion 1/2/31; preparedness emergency (See Comments) TI.I.- 549 II/l/80 FuII comptlance 4/I/81 plans to TI.I.-618 12/10/H0 See References App. E, 10 CFR 50

2. Heteoro- 6/I/81 2. 6/1/81 2. See Ti.I.-549, 1I/3/80, logical data (See h,.l e rencer,) Heuponse to Q22 I

Ill.D.I.1 Primary coolant 1. I.cak Complete 1. Before (:i it . 1: . R . 2.1.1.H . SER Section 2.1.6a outside containment rednction (See Coiwarnt s) ' d iscieu.cs 1.icensee

2. Tech specs 12/15/110 2. (See Com. ient s) .C"*Pliduce l1. Completion of tenting j jreiluiresplant conditions

other than cold shutdown.

8 l2.TechSpecswillbe ,,

g

pioposed 3 montlas af ter g ,

j complet tant of test program.

e ,I I  :

i

Attacliacut 1 - Het E i TMI-1 Het,[>onse t o NUREC-0737 T1.1.-680 1/23/81, Enclosure I requiiements items y, pig,,gg7 NRC NUREC-0737 NRC SPECIFIC LICEl;Sif. I.lCENSEE COHHENTS ITEM NUMBER ITEM AND SCalElsul.E TECilNICA1.

In SHORT TITI.E SCHEDUI.E l'ROPOSA1. C0tell l'l1ENT REFr:RENCES III.B.3.3 Inplant radiation 1. Provide Complete 1. Complete it . R . 2.1.2.1.1 SER Section 2.1.ffe monitoring means to R.R. / .1. 5. 'l ilisconnes I.icensee determine C4 nnpl lance presenice of radioindine

2. Moditica- 1 / 1 / 11 1 2. 'f l . D Eny,ineering not finalized Lions to (3;ee Connentu) L pincurement commi t men t accurately not available.

measure 1  :

III.I.3.4 Control-room 1. Review 1 / 1 / 11 1 1.3/Pyl II) TI.I. '152 10/20/80 I.icensee's evaluation is in p ogress. 1.icensee's 'l/H1 habitability 2. Moili f Ica- 1/1/81 l 2. Tl;D tion . unhmittal will identity I schedule for prudent modil'ication dertved Irom control room habitability review.

TI.I.-6t!O 1/23/til Page 17 of 17 FOOTNOTES Alliski:V I ATIONS (Attachments ! J.' and 3)

(1) Item represents a schedule change from R.R. - Restart keport previous Licensee /NRC correspondence TI.I. - 1.11. - Three flite Island I.leensing 1.etter S or Supp. - Supplument

( References to SER Section 2.x.x refer P - Part to SER Section C8, Lessons Learned Q - Question and Response thereto Category A numbering sequence. SER and SER Supp. l- NllREt;-06HO and Supplement 1 thereto TilD - To lie Determined (3)For modifications, the completion date shown reflects the date the construction and construction testing is projected for completion. Startup and test, technical specifications and training will likely follow these dates.

As noted, " optimistic" dates presume accelerated engineering, procurement (

construction and construction testing beyond that currently planned. Realistic dates based upon current engineering projections, procurement commitments and normal construction scheduling are later than these " optimistic" dates and are identified as " target" dates.

For modifications in 1982 and later, Licensee is proceeding expeditiously.

Ilowever, engineering, procurement, and the availability of plant cond1 Lions for installation must be firmly established before more refined dates can be established.

Technical Specifications are scheduled for submittal 4/1/81. In certain cases where the specifications cannot be complete, scheduled updates will be provided for each perspective change outstanding.

Attachment 2 - Met Ed THI-1 Reaguinse to additional 0737 Items 68

'II;I{3jg identifled in NRR I1]25]8) Letter (2)

Par,e,I oi I .

NRC NUREC-0737 NRC SPECIFIC 1.ICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND ScilEDUI.E TECHNICAL

& SNORT TITLE SCNEDULE PROPOSAL. COMMITHENT REFERENCES 1.B.I.2 Eval. of Org. & Before Restart See References TI.I.-380 8/25/80 SER Supp. 1 0 IV n Management for R.R.,Sectinn 5 discusses Licensee NTOL's Comptiance I.C.7 NSSS Vendor Before Restart See footnote 1 Review of Procedures 1.C.8 Pilot monitoring Before Restart See footnote I of selected EP's for NTOL's I.C.1 Pre-up & Low Power Training Regrs. Before Restart Hetore & during program results to be startup 6 test documented in Traininn program Records l'out no t es (I) Licensee has revised substantial numbers (2)AddItinnaI items from II/25/80 of procedures. Many of these procedures NRR Iciter encionure are covered have been submitted by the Licensee for in At taclu..ent 1.

B&W review. Numerous procedures have also been selected by the NRC (NRR and !&E) for reviews associated with modifications in analysis, hardware, or surveillance. Changes identified by either review will be suitably considered.

Since no specific NRC program has been identiffed, Iurther action by Licensee is not contemplated.

TI.I.-680 Attachment 3 - St at us and Schedule _ for Elv modi f icat ions 1/23/81 Enclosure 1 requirements items Paget ot4 NRC NUREC 0680 (SER) HRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND SCIIEDUI.E TECilNICAL in SHORT TITLE SCllEDULE PROPOSAL COHHITMENT REFERENCES ORDER ITEll #1 SER 07U 1.a.1 EFV pump auto start Restart Before >5% power (2) R.R. 2.1.1.7 SER O P.C8-34. Cl-l (5/81 target date) See A t* Nm2.1Ja 1/1/82(3)

NOL R.R. 2.1.l.7 SER O Cl-1 1.a.2.a EIN control valve Restart Complete fall open on loss Specified of air 1.a.2.b Backup air compressor Restart 'hefore >5% power II R - 2II7 SER 0 Cl-2 for EEN valves (3/81 Target date) 1.a.3 EIN pump block Restart tefore >5% power F.R. 7.1.1.7 SER to Cl-3 loading on diesel EEN tech. spec, for Restart 12/15/80 4/1/g1 R.R. I1.2.7 Formal request for tech l.a.4 flow and valve verif. spec change to be submittted Before >5% power SER N CI-4 1.a.5 EFV flow indication Restart 7/1/81 (7/81 Target date) R.R. 2.1.1.7 See 2.1.7.b Startup test to be peaformed SER (d Cl-5 1.a.6 EFW procedures and Restart Not .

Complete Psocedures SER 9 Cl_(, Procedure and training Specified (See Comments) training modifications will refIeet modIfIcatluns.

1.a.7 Surveillance Restart Not Complete Psocedures SER & Cl-7 procedures Specified 1.a.8 Control room alarm Restart 1/1/82 cfore >S% power R.R. 2.1.1.7 h lueluded in pump auto on EIN auto start S1, P2,t}6 start. SER O Cl-8 a

TI.l.-6HO Attacliment 3 - Stat us and Selieelule los l'.lv mo.f i f i c a t t ons I/23/8I Enclosure 1 requirements iiems page 2 of 4 NRC NUNEC 0680 (SER) NRC SPECIFIC LICENSEE I.lCENSEE COHHENTS ITEM NUHilER ITEM AND ScalEDUI.E TECilN ICAI.

6 SilORT TITLE SCHEDULE PROPOSAL. CONNITHENT REFERENCES ORDER ITEM #1 (cont.)

SER 0737 Hefore > 5% power 1.h EIN: Ind, of ICS Restatt Not 1/H1 (Target al.it e-) it.R. 2.1.1. / & Manual loading station to

!Specified lie installed lietore uRDER ITEM #8 i rentart(See also 2.1.7.a.)

2.1.7.a EIN auto initiation Restart 7/1/81 nefore > 5% power R.R. 2.1.1.7, Salcty grade pump start 31, pl,1)4 & on loss of 4RCPs or 2111'P Si, P2,all3 and auto start alarm -

TI.I.-500 10/2/80 See 1.a.I Safety grade pump start Additional EEU ltems 60 days 1.ong term ice comments on EU/St eam di f f erent l.s t of moda. on

s aid N OTSG level required by NRC staff .rHD.

(equilatent to 0737 matl. schedule receipt agreed to Sf- O'rSG mme item ll.E.1.1. long , , g term modifications) WILla 1 ic.

,,ontrol and lilock valves, cavitating ventuais CWSr level ludicatoru/ alarms, and OrSG level to be provliled lay Cycle 6 setneling.

A control grade OTCS level insttument independent of the ICS will lie provided belore Criticality.

2.1.7b EIN f low indication 1/1/81 7/1/81 See 1.a.S R . it . 2.1.1.7 Environmental qualification information to be provided

, when received from the

, vendor.

t l

TI.I.-680 Attachment 3 - Status and Schedule for EFM mt,dificalions 1/23/81 Enclosure I reilu i remen t s itens Pa ge__3 n f 4 NRC NUREC 0680 (SER) HRC SPECIFIC LICENSEE LICENSEE COMMENTS ITEM NUMBER ITEM AND SCllEDULE TECHNICAL li SHORT TITLE SCHEDULE PRDp0 SAL g

COMMITHfMT REFERENCES ADDITIONAL ITEMS (SER) S F.R 0737 - -

1. CWST level alarms Restart Not liefore > 5% power R . It. SI, P2, Alarms will not be frohn Specified (See Comments) yl0a independent power supplies before restart.

Inst. will alarm on loss of power and local tank readings will be taken.

2. EFW 48 hr. endurance test Restart Not Specified Before > 5% power R.R. S1 , P2 , Q1 Startup procedure to be submit ted and conducted SER 0 Cl-8

3. EFW Water source transfer Restart Not Specifled Complete Completed SER 0 Cl-9

4. MSL Rupt. detection system Restart Not Specified Original design R.R. St. P2, Q9 Completed. SER 0 Cl-9

5. EFW water source protection Restart Not Specified Original design R.It. SI, Pl. Q10 SER @ Cl-9

6. EFW indep of AC power: Restart Not Specified I 6a. Tit!) R . It . St, P2, Qi4 SER 0 Cl-9

a. 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> air Supp. I, P.2,

b. Reset EFW turbine 6b. TliD Q 31 & 13 safeties )

7. Upgrade EF-V30A/B for Restart) Not Specified 6/30/82(I) R.R., SI, P2 Ql4 Will not be completed steam break environment before restart due to j equipment delivery.

i vendor has not provided commitment date. SER @

Cl 10

8. EFW Cross tie break Restart Not Specified lie f o re > 5% power R.R. SI, P2, Ql2 NDE of the 10 higbent (Targeted for atressed welds to be

. lune, '81) performed.

SER @ Cl-10.

Engineering evalnatton anticipated in 3/81 for basis of weld seicetion.

- TI.I.-680 Attechment 3 - Status and Schedule for EFW modifications ~ 1/23/81 l' age fe of 4, ',

FOOTNOTES (1) Item represents a schedule change from previous I.icensee/NRC correspondence.

Safety grade start on loss of 4 RCp's and 2 IlFU i. umps is before restart.

Due to projected engineering f. procurement lead iime on safety grade OTSG 1evel insts, initiation on SG level is Cycle 6.

(3) Licensee is unaware of implementation dates for these specific items at specific plants. 1/I/82 represents 0737 date ior completion of i1.E.1.1 (4)

For modifications, the completion date shown reflects the date the construction and const ruction t esting is projected for complet ion.

Startup and test, technical specifications and training wilI likely follow these dates. As noted in "oprimistic" dates presume accelerated engineering, procurement, construction and const i nction testing beyond that currer.tly planned. Realistic dates based upon current engineering projections, procurement commitments and normal construction scheduling are later than these " optimistic" dates and are later than these " optimistic" dates and are indentitled as " target" dates.

For modifications in 1982 and later, I.icensee is proceeding expeditiously. Ilowever, engineering, procurement, and the availability of plant conditions for installation must be firmly established before more refined dates can be estahlthsed.

Technical Specifications are scheduled for submittal 4/1/81. In certain cases where the specifications cannot be complete, schedule updates will be provided for each perspective change outstanding.