ML20090F214

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Forwards Documents Potentially Relevant & Matl to Matters Under Adjudication.Documents Include Info on Reactor Coolant Pump Trip,Porv Corrosion & Emergency Feedwater Flow Devices - Controlotron.Svc List Encl
ML20090F214
Person / Time
Site: Crane 
Issue date: 06/29/1983
From: Baxter J
METROPOLITAN EDISON CO., SHAW, PITTMAN, POTTS & TROWBRIDGE
To: Chilk S
NRC OFFICE OF THE SECRETARY (SECY)
References
NUDOCS 8307050123
Download: ML20090F214 (18)
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.E wmTEm S DenECT DIAL NuesSase June 29, 1983 822-1090 Mr. Samuel J. Chilk Secretary U.S. Nuclear Regulatory Commission Washington, D.C.

20555 In the Matter of Metropolitan Edison Company (Three Mile Island Nuclear Station, Unit No.1)

Docket No. 50-289 (Restart)

Dear Mr. Chilk:

Since the Atomic Safety and Licensing Appeal Board has completed its review of plant design and procedures issues in this proceeding, copies of the following documents, which include information potentially relevant and material to matters under adjudication, are being provided directly to the-Commission:

1.

Letter 5211-83-174, June 8, 1983, H. D. Hukill, GPU Nuclear, to J. F. Stolz, NRC, Reactor Coolant Pump Trip.

2.

Letter 5211-83-163, June 6, 1983, H. D.

Hukill, GPU Nuclear, to.NRC Region I, LERs 83-003/OIT-1 and 82-Oll/99X-1, PORV corrosion.

8307050123 830629

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O CHAW, PITTMAN. PCTTs & TROWZRIDGE A pastNaseteese OF peOFttesONAL COmpo#AftONS Mr. Samuel J. Chilk June 29, 1983 Page Two 3.

Letter 5211-83-156, May 24, 1983, H. D. Hukill, GPU Nuclear, to J. F. Stolz, NRC, El'W Flow Devices-Controlotron.

Respectfully submitted, M

Thomas A. Baxter Counsel for Licensee TAB:jah Enclosures cc:

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TE'EX64 23E5 Wrt:s s Dire::D:alrw :e-June 3, 1983 5211-33-174 Office of Nuclear Reactor Regulation Attn:

John F. Stolz, Chief Operating Reactors Branch No. 4

-Division of Licensing-U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Reactor Coolant Pump Trip lur letter of March 31, 1983 (5211-83-017) provided infor=ation on our decision to revise RCP trip criteria from 1600 psig ESAS to 25 F subcooling margin and to implement these changes under 10 CFR 50.59 in June,1983.

The purpose of this letter as discussed between you and J. Wat= ore, on May 13, 1983, is to advise you that we vill join the other B&W owners in an effort to perfor= supplacental generic analyses to cuantify margins and to address more specifically the NRC staff guidelines centained in your letter of March 4, 1983.

Consistent with other B&W Owners, ve will provide su'ple-p mentel infor=ation and a schedule of our future activities in July,1983.

Sincarely.

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. i.*.' rites Oire:: 0.g; N.; -l:5-Jur.e 6, 1933 5211-53-163 Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, ?A 19406

Dear Sir:

Three Mile -Island Nuclear Station, Unit 1 (D!I-1)

Operating License No. DPR-50 Docket No. 50-289 LER 83-003/OlT-1 and 82-Oll/99X-1 Tnis letter -transmits update Licensee Event Reports Nos. 33-003/01T-1 sad

$2-Oll.'99X-1 concerning evidence of corrosion found on RC-V2 (PORV).

The infernation provided in the attached updated reports serves to suppler.a: t

-he previous reports (dated March 7, 1983 and October 25, 1983 respectivaly) and c1:seout the issue of the source of the FORV's corrosion and our c:rree-tive a:tions to preclude future corrosive attack.

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EVENT OES:MIPTioN ANo PRV8A3t.E :NSECL'EN:E5 g o,21 l During long ter= cold shutdown, the.ORV was re=0ved for a soecial inseectie

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corrosion '#cund in a previously installed ?0RV had not eccurred vi9

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io ii funaffected.

This is recortable oer Tech. Scee. 6.9.2.A.9.

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AusE OESORIPT!cN AN t i: 1 lCause cf cerrosion is attributed c acid sulfur :ct: unds.

See attach en: f:r I ldetails of transcor rechanisr.

Corree-ive acticns in:1uded:

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Recas~of LIR's A Power Operated-Relief Valve (?ORY 1) was re=:ved f::= :he SI-l Plan:

in;1981., This valve was sen: to 1yle Laboratories in 1952 for =cdifica-

' tion and=recertification.

Upon disasse:bly. :::csien of se=a inter:21 par:s was observed and reported :o G?US.

I:.:a=ina:10: of the par:s reveal-

.ed : hat the corrosion occur ed while the valve var in a closed s:a:e.

I:

appeared likely that the valve would no:. have functiered p;cperly as a result'of the corrosion.

This condition was ne: reper:able under specific Technical Specification require =en:s, 'but was repc::ed in LIR 82-Oll/99X-0.

The.second PORV (PORV-2), which had been installed in 1951 as :he replacemen:

for the one identified above, was inspected in February 1983.

This inspec-tion was: performed to ascar:ain valve conditic -in lish: of :he cc :csi:n observed in ?0RV-1.

So=e in:ernal parts of ?OR7-2 vere found :: be cc : ded.

Also, small yellow deposits (later-identified as 99'; pure ele = ental sulfur) were found-inside the main valve body.

The cc:: sic ebse:eed was si=ilar to.:ha: of ?ORV-1 but less severe.

It was judged, hcvever, tha:

the corrosion was 'suffician: :o have preven:ed prepar valve fun::icting.

This condition was reported under Tech.ical Spe:ifica:1:n 6.9.2.A.9 in LIR 53-003/01T-0.

It is.nc:ed tha: :he block valve was found fully capable of perfo:=ing its.1selatics fune:ics.

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Leading Circu= stances to the Occurrence s e ia' N. o. SLO: ^', ".as d..s ea.' ' e d.

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k service and refurbished onsi:e by a Dresser Indus: y service can.

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was no ed on the sur:. aces c: hese par:s.

the valve was reins:alled and was re=:ved f::= service in A; il 19E1.

Both PORV and Block Valve operated satisfae:orily during HTT in March 1979 in both open and closed posi:icns.

In August 1982, this valve was shipped to Wyle Laboratories for = edification and re:erti-fication.

3.

Description of Occurrence On. August 11, 1982, GPU Nuclear Corpora:1c vas notified by Wyle Laboratories that :he PORY vas co::oded and pi::ed.

Wyle took phe:o-graphs and wre:e a dese 1ption of wha: had been ebserved.

Unfer una ely, prior to testing and inspection at Wyle Latera:::ies, the ?ORY vas

horoughly cleaned with Radiac Wash.

Thereaf:er, he correded FORY parts excluding the valve body, which exhibited superficial pi::ing in several areas, were sent to 3abcock & Wil::x. f er f ailure ana* ysis.

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Leading Circu= stances :c :he Occurrence In April 1981 the ?ORV, Serial No. 3S03989, was installed en :he pressuri:er.

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_c t spec e s_ ca o,76.

s a..

n s.,..<....e.ne..eek c:

....; e we. e e cved.#c.

e=. s o....' a 4.s,, e c..d e..

. a

....#'._.'..a. co..es'.

.e-ported to the NRC by L_7..82-011 on an ecuivalen: :: del of this valve 5

was not occurring.

3.

Description of Occurrence Re= oval and disasse=bly of the PORV and 310ck Valve were comple:ed :

February 10 1953.

The pilot disc, pile: spring and pilot seat bush-ing were fcund corroded such tha: the pile: dise was stuck in the full o p e p o s 4_. 4 c,...

'.f'b. a. v0v.b d4.se was.:c.

d c

..,;e;

)....... c k.. o. L..,.

3<,.. _ _.

=-

o in the closed rosition.

Additionallv., small yeller deposi:s were found on the internal. surf aces of the- ?Op.V and in the Block Valve caviry.

The following is a. s-=ry of the as-found conditions of the internal parts:

3)

v. u...,4. lot da_ s,. s p _. 4 g., c a <, d a_s,. _ _ <,,. <... c...,. -

.c., m:. -

m.

c:rreded.

.)

. : e _r _., o s. a. e t,.s n < _..,. (... - c,..e.,

4. ym _... <

T.

-as e..o'c.'

s

...c...

s.uch.c... n c,. _a,,. d<sc, pi_,o.

c.a. s -,- _. _a. _......

..e.

s,e_..2_..

a o

o

=.

a)

.e

<, _ sa

- sc, _c...

s <,a,e, g < :.... < _ <..e..,

_2_

. :. s _...

3

a.. '_ ' o i. '.-. e u' '. * *. C.

=..... e _'. 4 - s..'...'=..=.=.=.=.=..~.=..._s'.

..e.,.

..>e;.

+

_..,._-,<2.e..

.. e 2., r.e., _ _4., g _....,.. 4 a., )..,,,....

-)

r s.._

3....

=.::_~.

m.....

=-

e..

~

.u..,..,..<._<__..

. 4.. e :

.=

_:.._4.,.

s.-

- _. o _... e.

. e

.__...,4s.. n. :..

c.:

.,. z.., :

)

s..

_.........._....a_=_

..==_

4.=.

a_.. : u.....

s. scc o...e.

sn

...:.e.,......., =

....,.....,..,..,=:.,.,m.._..:

.- s... :a c., s c.=... e. c. =.. s

=

,)

..a_.._ess s.e#.1_...-. e... _ \\, s*..~.e'-..:-.=-...=-..'-.-.~.~.c'-..'.s-...%:.

.....s=:.:,...,....<.,.-----=...:.

. e.,,

...e :. o,.. >...... - -,.

(...

s. 4.

..:._e_

.., 4 -)

._....c n,

,_a3,.

.e.,.. 2. _., ;

s. u..__4..a...

'.._. :. o..,........ z. e _.. r. -. '.

c.)

....s.

.. =

. s

..e

.__..<n,.

3

'h

F 3

a.. S s0.S.S / o. c. ). O t ;.. c.s0 3/0_5. 0 II; Evaluation of Conditien & Cause - cen:inued Sa'a-ed.DO*..V ra.. s.. e p. e s.n. ' n g.'.. e v.-. '. -".s

-... ' a ' s ~.#

-.... =.... -. '....

.for :he' valve in:ernals, and :he yellow dep:si:s fren both va'.ves vere sen: :o Battelle :(a=orial Ins:1:u:e for ne:a'lur;ical and che ical anal'tsis.

Highligh:s of the Sa:telle s:ui are de: ailed bele":

1)

The yellow deposi:s were identified as 99'; crys:alline su'. fur.

2)

.ne po_o asw_sc..as s.uck. <

. e ope a_._a_._ - e. c n.u.. _._. a_ _n....

cf corrosion produe:s.

3)

The guide was s:uck to -he =ain disc by a vedging effec: :rea:ed by corrosion produe:s.

A 2000 pound Icad app'.ied :c the disc face con'.d

. not move the disc inside the guide.

4)

In general the main disc, lover spindle and pilo disc were pi::ed.

In addition, inor cracking was associa:ed with so=e of the pits in the main disc.

5) patches of intergranular attack were presen: a: :he inside diana:e surface of the bushing.

6)

The guide showed no evidence of corresien da:a;;e.

7)

The pilo disc spring was pi::ed and cerroded.

-)

.ne oc..o o_.he p4s.o

...s s.,<.3 c

9)

No corrosion a::ack was

.ese... c...'....

'.d.'_i-.. a s a

d. - a".-. =.......

~

stainles= steel (19 Cr, / N1).

.e. )

.c...,:.a. s.as

.--n-

.an a.,1 co

,s<on

,..c....e.

... 3 _. 3 2...

... a

.,... =.. -

..a. _4c_s.:.

.o 3 n,.

s..

s_-)

s. e.s..., e e.c es "e. e d e *. e. e'. '....'.. a.

-..... = '.. -......#"__-__e.

.-8 a

A.,,. c n..

s _n,....., c _ a :... _2 : a. n. a.,.,...,......:.a..,.._

e....

... =...

s._.. : : a_.- asa...

...:a..s,

~:...
_ c... :.....

...... a.

..es,

=

..=..-...:

a:

,pn a,...

o g ce.... :.... a.a,

a.

..:...........=...... =...:

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

m.--

e.-

,..-e...,. c.: n...., c e.

..--..e..

. e..,,,... at,.s e,.. u..e

.o s <.o n a s 3.,.,.,_..

... a u.._. _, 2 a.

.e... :...

.,......: s.

g a s a c.. s s.., :.......s.,

u.. :. _ e_ z.. s.. =..

s.=...

a..

a

=.

....:=...

g. _,,, e. o e...,..

4_..

.ne..esa.. e

~.# --....e'..-.

'..... =.

0. w' ?.."..

~ '.. =.. =..... =...

..-~- _...c ves b.e Je-n. pcc'.*.-.. c.'.*..'os~--.*.-.=.'....-_=.==-"c

. ~ ~ '. ' "... =. =... '. =.. =.

~

. c '..- %. '. a. s"1."t.

-.-.. ' '. e c...... 3 e.. s u '_.......... -. '....c =.. =.. '.. '. =

c s u,.:.,..'.. s 4.,,.. e c 4.

'.. =. ~..

3 s ; e..

_ s...e

.u....

e..=.2.

-%..e _c e a s e s we u' d s".%. s e.u a.....'.. ~c e...-...e,,... =. '.. -...=...."..". ". '.. =.. =.. '.. =.. -

~

.:C.

Co

,st.e sC_..

2

. s... u..

.- e.

n a _.= :......n..e-4a..

..~..a
2..:

-.. w.. :

e..,

,s..,,,

sc._... t, s.. t.. ; ;., e.:. e,:...,.

a

....:,...a..

- -. =.._

.........a.

..u-s ~ ~. %.. g

.ea.,,

.e.. s....

...s

......a...

..~...

3 4 a..e.

3 an s.,

u..... s.. 4.,....a i.,. :

a..

1

" I.I'v-E2-011/ 9 9X-0 j

't.Ii 53-003/Oli-0 II.

Evaluation of Conditien 5 Cause - con:inued D.

Previous-Events cf a Si=ilar Nature The ?ORV, Serial No. 31.08905, which was res:ved f== service in 195; e):hibited si=1lar cc osien (perhaps a li::le :::e severe in s::e areas).

See LIR S2-011.

Decon:a=ina:1on of these c::::ded par:s had re::ved any che=ical evidence which =igh: have 1.: dica ed the cause of :c :: site a

act. o..ha. N,a.,va.

=... eve.,.<

.,s

....e..

a.-

findings, it is now helieved tha: the-::::: den: respensible fer :he corrosion of this valve verv likely was a self : species.

i

/

6

)

O b.

u-m

e. e.. S.e_ m.. / s. eJ v._0.

i w

d

  • 1.u....e.2 e.0.e, / 0.S -0 v
v..

nd.'.'. d. e.. a 1 o'. '_ c". -O..

N... s a.

. d.c.. e The 20RV is ins:alled on a pressurizer ne::le ::.nne :ed :o -he s:ean spa e.

Ad d.* *. * ".n a.'

".. s o. e c. * -.. s ". e. e p e..'-. - = '..'

.'.. = ~ c c r.. *.. s an. '. 7 _ e _'.. -

c 3

which also connect to the stes= space.

These were felleved by a anned entry o.:.he p essu.<.e. :o

u.u..e. a...se,.ae..c..

._,...a..

- e : n

n.. <.. 3 ;,.

3 cribes.the resul:s of these inspec:1ces:

Tv: safety valves are connec:ed :o ne::les in :he pressuriser upper head.

z.. <,, 9 8 >, t h e e, y e., s e e.a., ; :. -

. u..e,. =......<.,..

u.,:.

s...

= =.....

.- '-c

.ca '. _.. ~. '.. =.

piping.

Both valves and :he tre sections cf leep seal piping were visual y_

exa=ined for corrosion.

Safe:v. Valve RC-RV-1A vas f:und to have no ec: resten on either the nozzle (347SS) or dise (Incenel-X-750).

Wipe sa:ples were obtained of white deposits and a black fil= f:und on the valve inle:.

Safe:7 Valve RC-RV-13 was fcund to have no corrosica ce he ne::le bu: had s=all, shalloc pits on the disc face; the seating surfaces were no: da= aged.

"ipe sanples were obczined of the yeller deposits found in the area.

Analysis of both sets of vipe sa=ples is pending, bu: is expec:ed := shev sulfur concen::st,.ons ana. gous to these :.cund ce :.ne _ce; seaa,s.

spe:: :

c:.

zo the loop seal piping (304 SS) revealed ne cer :sien bu: the wipe sa:ples did c c....* ~.. su 1.* u-.

. n e s. e.- ~ ~. o n e s o

  • b o. h ~. * =. =.-. '. ~. *.. =. "..-. e. ' '.. =. '.' ~< ' =..*.

had less,han 400 pg/:e2 yn..n.....e ya.e. _'..=. a...

s.

=.3=.d a

..-..=..=--...-r had about 2000, g/f:.

The reason for the difference between :he :v0 lo:p seals is not knou-. bu: =ay indica:e that ene :f he loop seal.= vas ics: a-scue, point.

The deposit analysis results cc:: alate vi h the valve insre::ic resua:s.

. h.. -. e s s u '. e. ve.... a ' v e (D..C-V 7 'a )

.s "...e, =_-. =..' s '_.. - =.... ' s V. ' ~. =.." s a

.d.e 4

.r c c... =. c. e d. c

..%. e 3. e.c s..*. e. s. =_ =.

s., a c e ~. '.. ~..~..*. ~. *.. =. ~. = ~.. ~.

' 7 _...

~~.s..-..'.-.

3 o.:. u...ss.. 1,.e e..e. c.c s... s._? _n.....a..<..

.u.,_..._...

.a-s _ _.-.

7...

.=

..a

u.... n.n.

..o a e3.,.e y..anh.

u g

ec. va_, __....a... c.

.a,. e 3. a._.,.

~..

.=

pressurizer spray valve (RC-V1) was also inspe::ed.

RC-Vi is nc= ally

.,. ;,. c, o u...,u. :.

u....e

, e en e,.,... e c. c u..,.

. :..... a _... 3.

=-r.=.

-..=..

..=

==.._ :-

=

s.ac t a s. = ~. '....~ ~. e c' u r~ c n s'n. '

.m...

1u.._'_<

..:-..=:.......'.-..-.>.=-__:_.

s _

de:csics on the -.essu '..e.

c'.'=..#

. '.. =.".s.".=.. -.... -..-..c_e_.-...

d e

. e

....ec e.,.

a.,..

ne

_f ess..

a..,.

.. a_.. :. a......=...__._..- a

.,e

..=,.....

,.'7 _~..c. a..d ~..~.~ '. s.,

~. *.. e - h. e ' '_ '... =.....c ' s.*.-=..=..s...=...=...

" =._.'.=. '..-..'..=.

e.,

.,c

. =

-...e=.. a e u..

=..._a..a...

.==.... :.

. e _. :.......

a.=...:

e s..

..c.

..-.,.,a..... c

-..... :. u..,. a... :.._...

. z a. u.. _,... _

.a...

..... g..

a.

.

.=..=

..,.-,...,_=2....,.

e.

c,.,.. a.,

a..

...a__

=. _,...

.....,..._.e

.=...

.3

.. = _ =

.'. '.. e s e a. e. '. _ < '_ =-

=...d '.~.. c. *... ' c c e.-. =..'...c'...".

'. ' '. -. = ". ' "... -... - =... -

.r

..._c...,

a

..a

... e..,,

2.,.,es......:

2._.c s.

=.:...

....a...a...

s o.,.-. _:._

r b. -....: a.,...

...asc <

.es.>

..e.1 s.... <_..

a..

.: _... =... = _

=-7..,.

, a. _, a_...

.=

sn:vac no de:.e::s.

4

.s 1

I I

s E

  • "T..

C *..* 9 _9,/ c. C. Y. 0 u _~.. c.e. _ ~ e s~

01._n.

!!I.

Addi:denci Tellev-On Inscee-dent - centinu e'd -

Welds in :he one-inch vent piping near the pressurizer were radic.::aphed and did no shown any defects.

  • clerasonic :esting and radicsraphy per-for=ed in March 1982 showed the spray line :hern21 s_eeve and surge line

-no::le safe end (Incenel 600 and 316 SS) :c hate ne indica:1ons.

~he conclusien drawn fren these inspecticns is : hat, with the er.:epti:

... c.= ~- ~.. c ~. ~r '.. 4 ~.a g ~.. o. a * = =. c. < _ ~ s ~; s ~. e~ '.. >. g..'. ~; -.

~ ~ '.~.,

.h. e '- = -a-

=.

s s

is confined to the ?O7.V internal par:s.

D A

v 1

e Ol

'L R El-011/99%-0 tr e..t_00, 014 0 IV.

Ccrree:1ve & Preventative Ae:icns PCRV-2 was disasse= bled as discussed above and exa=ined fo.

.... sics.

The. valve body was cleaned':o re==ve any residual sulfur and dye pene:ran:

j

es:ed.

All of the ?ORV i=:ernal par:s were rap'a:ed during reasse=bly.

i The reasse= bled valve was ni: regen leak tes:ed and fun::icnally :es:ed pri:r to reinstalla:icn.

The bl::k valva (RC-V2) was a* se cleaned pri:: ::

reins:alla:ics.

All c:her valves were fun::i:: ally unda: aged and no corrective ac:icas were recuired.

The pressuri:er internal surfaces were cleaned by hydrola:ing a: :he ti=e of the =anned en: y.

Visual exa=ination fell:ving hydrela:ing sh:ved tha:

the corrosion products and yellow deposi:s had been re=oved.

The FORY discharge tail pipe and reactor coolan: drain :ank were also cleaned a: this

1=e.

Re= oval' of residual sulfur fro = the re=a'ning ;:r:icas of the Fea::::

Cocian: Syste= will be co=ple:ed pric: te plan: heat-up.

This, in c00-binatics with the. pressurizar hydrola:ing and eli=ina:icn of :he sodiu:

-u..'.c s u '.*n ~. e a d A 4.*.ve,

.-'.1_' - ' n ' _*_ e ~.h. e ~e ~. =.... '. '.=~~.. e~~.~.. e. ~=..~.=

s".

assisted corresien.

React:r Coolan: sulf a:e ~ evels will be :: it: red

o ascura early detec icn and pro =pt eli ina:i:: cf pe:en:ially corresive conditions.

n addition, a follow-up inspe::i:n cf the ?0RV will be per-

~

for ed in conjunction with :he first post-c; era:ic OTSG eddy curren:

exa:ination. (?er Topical Repor: 008 Rev. 2, Appendix A Sectica I!!.3) a w

4 6

4

7.. :. c.9 013 / c. c.s_0 us.s ca-00.w.. C:

2.v..-

V.

Su==ary & Conclusion

~

Licensee Event Repor:s 82-011/99X-0.'nd 83-003/C1!-0 re::r:ed findin:

corrosion of :he internal parts of t o !XI-l ?ORV's.

The ?ORV's were installed sequen:1 ally and covered the operating periods April 1976 ::

April 1951 and April 1951 to February 1983.

Io:h valvas e::hibi:ed si:ilar 1

_i corrosion of the internal =artensitic,Inconel 600 and I:enel X-750 par:s; aus:eni-ic parts were not affected.

General corr:sien and pitting a::a:k w4 c.. n some oca;.4:e:.,s.;ancs c:...

A v.-

were the predom.4nant corros4on for

=

obse rve d.

Examination of the corrosion products and deposits frc: the second FORY t_

revealed that the corrosion was due to attack fro: a acid sulfur species.

The corrosion cost likelv. occurred at low te=rera:ure al: hough the n

sulfure transport cay have occurred either he: or cold.

A detailed deternination of the responsible corrodan: could n:: be =ade for the w

li first PORV but the similarity of the attack strongly suggests that a 2

si=11ar techanism was ac:ing.

Thiosulfate in the Reac:or Coolant appears :o have been the source of tha corrosive species.

Extensive inspections were perfor=ed of other co=p:nents connected ::

the pressuri er and of the pressuriser in:ernals.

Corrosien in these other co=*eonents was li=ited to so=e isolated cases of ninor pit:in.:

which did not affect sys:ec func: ion or integri:y.

Thus, it was con-cluded : hat all significan a::ack was confined :: :he ?CKY.

Corrective measures were undertaken to res: ore :he POK" :: Operable s:a:us.

The valve bocy was cleancd and thcroughly ins;a::ed.

All valve internal parts were. replaced.

This final valve assembi; was :es:ed and has been reins:alled.

The block valve, although no: c:rredad, was similarly cleanad and inspe::ed prior to reinstallation.

_b Residual sulfur has been or will be removed fr: :ha Rea:::: Coolan: 5 s:er uwS 5 ze...e.c.e.

c.

....:u<-.

o u e c-.. e....

- a, <.. a

. e e....e.. =.

w..

u-e.

=

he FORV and block vlave, the pressuricer in:*rna surf a:es, the ?OR' dis-

-.2.,,a-2.;.

.2

... a n 2.a <......

u 2

C..a...e on.4.,,4pe onw ne.es.,.

.o o

s.,.., c. w_~ec eC cs a

.. :. : e... -

. =,. S -... =

s.

. e -a-t.e...: e o I-ne

.~% v.

~c a.

^

  • .- e e

. 3u

.,.-a.

.., - a. s.e.

g...

..-. i.

2u-2-.e.-.

..e..d...

w..e e s..y

,,. 4 o.e.. 3

s. c.

.2-

..e 2

.n 3

2 r--c c.

2-g....

and el' 'na:icn cf pc:entially c:rresive envir:n.an:a.

-: addi:icn, ::

~

assure :ha: :he corrosion is nc: ccarinuing, ::.c ?:FJJ ::11 he inspe::ad i-

  • 4'-.'..

.h. e.'.'..c ~. ~ c s ~ -o v. e ~. c- ~.

  • c.. O'. S ~ =- ' '. -.-.=..es '.~.

c o ~.. ' "w...-..'.' ~.

-~

3 r

W

  • t

W

'd 3

GPU Nuclear Corporation f

f 's

. A ps:

Pcst Office Sex 430 W

%r

's

ute 441 Scuin u

i t.';cc.e: wn. :ennsy:,ania

  • 55 7 D 7 c44-762; TELEX 84-2336 Wnters Direct Dia: N rn::e-May 24, 1983 5211-83-156 g

Office of Nuclear Reactor Regulation Attn:

J. F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington,.D.C.

20555

Dear Sir:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 EW Flow Devices - Controlotron As part of the Emergency Feedwater System (EFWS) upgrade GPUN committed to install by Restart, safety grade flow devices which indicate in the Control Room.

To meet this commitment, GPUN installed 2 Contro1otron sonic flow devices on each flow path to each OTSG.

This com=1: cent was found accept-able by the NRC Staff in the Restart SER (NUREG 0680) and the ASLB in the

-PID.

The physical arrangement of the "B" EW header has resulted in interference (cross talk) between the 2 detectors which has prevented them from operating properly during the preliminary testing phase.

Efforts to date have been unable to eliminate this cross talk problem.

Due to different physical arrangement, no such problems exist for the Controlotrons for the A OTSG.

GPUN intends to operate with one Con:rolotron for each CTSS energiced uhich will eliminate the cross talk problem.

Additienally, the other " low enannel for each OTSG will be provided by a differential pressure system.

GPUN will ins:all safety grade differential pressure transmir:ers ento the existing annubar flow tubes prior to Restr.rt.

This system will read out in the Control Room.

This modification to the E W system flow indication meets the requirements of Restart Report Section 2.1.1'.7; SIR (NUEIG 06S0) dated June 1980 pp. Cl-5, CS-39;. Partial Initial Decision dated December 14, 1981 p. 229:

and NUREG 0737 II.E.1, Part 2.

Sincerely,-

i

/

r y

N

h. D. Nuki.ll ec: J.1 Van Vliet Regional Administrator GPU Nuclear Corporat:Ca is a st.05 e ary Of tne Ge e's e _: :,, * :ti ~-*r-i

o UNITED STATES OF AMERICA

~ NUCLEAR REGULATORY COMMISSION In the Matter of

)

)

METROPOLITAN EDISON COMPANY

)

Docket No. 50-289

)

(Restart)

(Three Mile Island Nuclear

)

Station, Unit No. 1)

)

SERVICE LIST Gary J. Edles, Esquire James M. Cutclun, IV, Esquire Chaiman Office of the Executive Legal Director Atcmic Safety and Licensing Appeal U.S. Nuclear Regulatory Cmmission Board Washington, D.C.

20555 U.S. Nuclear Regulatory Cenniasion Washington, D.C.

20555 Docketing and Service Section Office of the Secretary Dr. John H. Buck U.S. Nuclear Regulatory Cmmission Atcmic Safety and Licensing Appeal Washington, D.C.

20555 Board U.S. Nuclear Regulatory Crmninsion John A. Levin, Esqture

. Washington, D.C.

20555 Assistant Cbunsel Pennsylvania Public Utility Cmmission Dr. Reginald L. Gotchy P.O. Box 3265 Atcnic Safety and Licensing Appeal Harrisburg, Pennsylvania 17120 Board U.S. Nuclear Regulatory Cemniasion Dobert Adler, Esquire Washington, D.C.

20555 Assistant Attorney General 505 Executive House Ivan W. Smith, Esquire P.O. Box 2357 Chaiman Harrisburg, Pennsylvania 17120

- Atcmic Safety and Licensing Board U.S. Nuclear Regulatory Comission Ms. Iculse Bradford e

Washingtcn,.D.C.

20555 TMI AIEBT 1011 Green Street Dr., Walter H. Jordan Har,-inburg, Pennsylvania 17102 Atcmic Safety and Licensing Board Panel Ellyn R. Weiss, Esquire 881-West Outer Drive Harmon & Weiss

' Oak Ridge,. Tennessee 37830 1725 Eye Street, N.W., Suite 506 Washington, D.C.

20006 Dr. Linda W.'Little.

Atcmic Safety.and Li nsing Board

Steven C. Sholly-Panel' Union of Concerned Scientists 5000 Hemitage Drive '

1346 Connecticut Avenue, N.W., Suite 1101 Raleigh, North Carolina 27612 Washington, D.C.

20036 O

^' l r p

. Jordan D. Cunningham, Esquire-j 2320 North Second Street Harrisburg, Pennsylvania 17110 ANGE/'IMI PIIC 1037 Maclay Street Harrisburg, Pennsylvania 17103 William S. Jordan, III, Esquire Hamon & Weiss 1725 Eye Street, N.W., Suite 506 Washington, D.C.. 20006 Chauncey Kepford

- Judith H. Johnsrud Envimmmad.al Coalition on Nuclear Power 433 Orlando Avenue State Cbilege, Pennsylvania 16801 Marjorie M. Aamodt R. D. 5 Coatesville, Pennsylvania 19320 e

15'9 T

6

-

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