ML19208C764

Notifies That Mods Necessary for Facility Restart Will Be Completed by 790901.Reactor Will Not Be Restarted Until short-term Items Have Received NRC approval.Long-term Mods Will Be Completed on Expedited Basis

ML19208C764
Person / Time
Site:	Three Mile Island
Issue date:	06/27/1979
From:	Herbein J GENERAL PUBLIC UTILITIES CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19208C759	List: ML19208C758 ML19208C764
References
NUDOCS 7909270418
Download: ML19208C764 (6)

Text

& GPU Service Corporation

r --

j g; @,gU'sm V >=-]egQ'e r 260 Cherry Hit Acac (f c.d W Pars::cany New Jersey 07054 201 263-4900 TELEX 136-482 June 27, 1979 Mr. Harold Denton 00C Director of Nuclear Reactor Regulation 6 #c y U.S. Nuclear Regulatory Co==ission 2 g \h ,, 1 g gb cO%- ggd.S# qv ,*

Washington, DC 20555

Dear Mr. Denton:

Y O

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, g, ,,/

UNIT 1 (TMI-1) '

OPERATING LICENSE NO. DPR-50 DOCTIT N0. 50-289 -_

Sy letter dated April 16, 1979 (GQL-0576), we committed to providing significant advance notice prior to taking TMI-l out of cold shutdown. We have identified a number of Modifications / Actions to be completed prior to the.

TM1-1 restart. We expect to be able to complete these changes on or about Septembe r 1,1979 and it is our hope that we would be able to receive the necessary approvals from the NRC to support tha schedule. However , the reactor will not be restarted until items 1(a) through 1(h) below are com-ple ted and we have received your approval.

1. Modifications / Actions to be co=pleted prior to TM1-1 Star:up (short-term):

(a) Upgrade of the timeliness and the reliability of :he Auxiliary Feedwater Sys:em as described in Enclosure 1. Changes in the design will be submitted to the NRC for review.

(b) Develop and implecent operating procedures for initiating and controlling the Auxiliary Feedwater System independent of the ICS control.

(c) Install a hard-wired control grade reactor trip on loss of main feedwater and/or turbine trip.

(d) Develop and implement procedures and instructions to define operator actions for small break loss of coolant accidents.

Rev iew recent B&W analyses of small break loss of coolant accidents and confir= their applicability to TML-1. &

LO (c) Augmented retraining of all Reactor Operators and Senior Reactor N Operators assigned to the control roca vill be conductec includ-ing training in the areas of natural circula:1on, small break O

, loss of coolant accidents and the TM1-2 accident. All operators hy( will also receive training a t the 3&W si=ulator on the TMI-2 accident. Met-Ed will conduct ICC" reexamination of all opera-u

y.G[

s tors.

~

, , - - . - - . , . - - - . - c. - .. + . . n .

7909270yf

JHAW, PITTMAN, POTTS & TROWB RIDGE The IIonorable Joseph Hendrie July 2, 1979 Page Three Mr. Herman Dieckamp and I plan to be present at the Commission's meeting today and we would be ple& sed to answer any questions with respect to this request.

Sincerely, M

eor e F. Trowbridge Counsel for GPU Enclosure cc w/ enclosure:

Commissioner Victor Gilinsky Commissioner Richard Kennedy Commissioner Peter Bradford Commissioner John Ahearne Samuel J. Chilk, Secretary Leonard Bickwit, General Counsel t

R

~

1049 260

. N 3 , %d E =' .

• USNitC ENCLOSURE 1 I -- g g"[3

• getM OthCS goCK M Cl D3S "

s AUXILIARY FEEDWATER UPGRADING -

x .. .Brant y

.o

1. Automatic initiation of the motor driven AFW pumps upon loss of both fe.edwater pumps or loss of four (4) Reactor Coolant Pumps.

2. Modification of the AFW control valves such that they fail open on loss of air.

3. Automatic block loading of the motor driven AFW pumps on the diesel.

4. Incorporation of AFW in the TMI-l technical specifications as specified in IE Bulletin 79-05A, item 8. Verification that technical specification requirements of AFW capacity are in accordance with the accident analysis will be conducted. .

5. Provide indication in the control room of AFW flow to each Steam Generator.

6. Provide procedures and training to assure that AFU is avai.lable and properly applied when required. Procedures will identify the need to verify proper operation when AFU is initiated.

7. To assure that AFW will be aligned in a timely canner to inject on all AFW de=and events when in the surveillance test code , procedures will be ,

implemented and training conducted to provide an operator at the necessary location in communications with the control rco: during the surveillance mode to carry out alignment changes necessary upon AFW demand events.

8. Desi;;n review and modifications , as necessary, will be conducted to provide control roo annunciation for all auto s tart conditions of the AFW system.

lDTIM o e-a

[.D '] [j; O

i [h I c au m L W h

...s 1049 261 ns t ;mi m

(f) Co:plete : hose addi:ional items in Enclosure 3 designated as short :ern.

(g) Upgrade :he s:a: ion emergency response capability as described in Inclosure 2.

(h) A degreed ' shift" engineer will be on si:e a: all -ices during plan: operation to provide additional suppor: and advise shift operating personnel.

In addition :o :he above shor: ter: improvements, Me:-Ed reques:s the NRC to recer:ify the TMI-1 opera: ors. Further , Me t-Ed will accomplish the below lis:ed long ter: iters on an expedited basis:

2. Modifications /Ac: ions :o be completed on an expedi:cd basis but not necessarily before startup of TMI-l (long erm):

(a) Provide , as soon as practicable , a f ailure code ond ef f ec:s analysis of :he ICS. (This task is underway with high pricri:y a: 2 2....,. .

(b) The harc-wired : rips referenced above under ite: 1(c) will be upgraded to safe y grade in so far as practicable.

In addi-ion o -he ab:ve shor: :er: and long ter: 1 e:s, Enclosure 3 also

......a,.,e.

r.a.. ...a.,.

. c :. a -a..

u . . a..w - . . ,, . . . . . .. . a. >. ,.y. u.,..

. . 4..g., . - => .: , .., ...was- ., g e - n

. . .. r , < .+. .

. . ,. , e

..,,,.s, s,. .w_.

. ,1 . :. \. e , . .a.e .s .' . t . . u. . ,..

e  :..

.>.c.... ., . .i a. C .ec .u..s.1.e ._.; s

.. u ,. c

. .1 a as.1. .; c .:. . .u..,.

a . , .

riac Or ;c rispond C Various :rInsien even*s.

g ,. ., .,.9

. g. ....; }. g ..a

. C. F.erbein

'.'ic e ? r e s id e n:

J ,. , .v.7 / e : s E". closures c:. '.:. . , .

.t e t :

u[0 @ m m W

) '

,P ; 4., ! ~

. j \f i-l r i t.'

, t; , 4 ,

A m. .' !luuu hi i I i

i

o. -

1049 262

E: CLOSURE 2 EMERGE:;CY RESP 0:;SE CAPABILITY GPGRAt."1;G

1. Pr /tde the capability to supplement the shift and emergency organization

.tsonnel with a Met-Ed/GPU organization for off site emergency support when called for by the Emergency Plan. In addition, provide for a compre-hensive organization to coordinate long term accident recovery and pro-tective action.

2. Upgrade cc:=unications on site and off site in and to the TMI E=ergency Control Centers.

3. Provide additional emergency equipment including respirators, dosimetry devices , and monitoring / analysis equipment. Significantly expand the radial and az=uthal distribution of TLD's as part of the routine radio-logical environmental =onitoring program.

+

9 jF6r)fET OP oo na m

j . t j I 4'

,, - 1 r

, : , f')I ilb.! ,,t'

- ~m __t .m . . _;

l0'. * ;' O f 1049 263

/ . 2. ./  %

. E:' CLOSURE 3 d, OTHER MODIFICATIONS TO BE COMPLETED BEFORE STARTUP b}

ca.

t o Ib , p*

/(

l--

• o OR AS SOON AS PRACTICABLE THEREAFTER '

<Gj M.o ,-}-

p g.x,;t d,,],'- p;* {2 A. Before Startuo (Shor: Term) b , Y.. :nd

.n

1. Reduce the high pressure reactor trip to 2300 psig. C

2. Upgrade selected instruments and valle operators in containment by applying heat shrink tubing to electrical connections for water t ig'.:ne s s .

3. Hookup 16 incore thermocouples to the plant computer with readou capability to 2300*F. .

4 Revise contain. vent isolation signals to isolate all lines which do not degrade core cooling upon initiation of HPI or other appropriate signal such as high radiation.

5. Revise valve position ino! cations to show actual v;1ve position versus demanded position on all appropriare valves.

6. Improve plan: co=puter printout and alaru capability. ,

7. Raise the PORV setpoint to 2430 psig.

d. Provide an unambiguous indication of PORV position.

9. Provide remote essential maintenance for the decay heat removal pumps to =inimize post accident personnel radiation exposure and i prove reliability.

10. Install a H,> recombiner with provision to hookup a second one.

11. Install the approved HPI cross connection to eliminate the need for prompt opera:or action af ter small break loss of coolant accident as described in our letter dated I;ovember 21, 1973 (GQL-1619.

12. Raise selected Stesa Generator level ins:ruments to 72 inches above the containment floor.

13. Complete modifications to provide TMI-1 sampling capability indepen-dent of T'11-2 and to isolate the TMI-l Fuel Handling Building ven:ila-tion f rom TM1-2.

S. As Soon As Practicable (Long Term)

1. Hookup all 52 incore thermacuuples as specified in A.3 above.

2. Iaprove plant computer data and trend display capability.

y' M m ![,f tjFo? @@

if;,

s jui or W Mui rqFr$nrOd

$U M= 1049 264

3. Install an instrument to alars and indicate RCS approach to saturation conditions.

4 Increase the range of RCS temperature indication for the hot and cold legs.

5. Auto = ate switchover of the ECCS pumps from the 3'JST to the Reactor Building susp.

6. Upgrade the Reactor Building Spray system to eliminate sodiu: thiosul-fate addition.

7 Upgrade the coating of the Reactor Building and Auxiliary Building lower levels to reduce penetration of radioactive conta=inates where additionally required. .

8. Provide for Reactor Building sump level ceasurement and sampling.

9. Provide a system for waste gas tank venting to Containment.

10. Raise the pressurizer level instrument ;o 72 inches above the contain-

=ent floor.

e 1049 265