ML20010H850

Forwards Clarification of Inservice Insp Program,Tables D-1 & D-2

ML20010H850
Person / Time
Site:	Crane
Issue date:	09/25/1981
From:	Hukill H METROPOLITAN EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
L1L-264, NUDOCS 8109290354
Download: ML20010H850 (5)

Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _

i i

9 Metropolitan Edison Company Post Of fic.e Box 480 l I- -

Middletown, Pennsylvania 17057 Writer's Direct Dial Number September 25, 1981

. q,\\ g Q-i LlL 264

/Q f

k (i

0L.'J$ g &

Office of Nuclear Reactor Regu.'ations SEP2 319815 Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 3; pa 3 n.

4 U. S. Nuclear Regulatory Commission f.

Washington, D.C.

20555 c6f

Dear Sir:

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

Operating License No. DPR-50 Docket No. 50-289 Inservice Inspection Program REF:

1. License Amendment No. 71 and SER

2. Met-Ed Letters GQL 1357 and TLL 032 Our review of License Amendment No. 71 has revealed several items which we felt needed further clarification and in one case further relief.

These items are detailed in attachments 1, 2 and 3 enclosed.

Sincerely, i

Q l

'th D. libkill Director, TMI-l HDH:CJS:vj f Enclosures cc:

B. H. Grier D. Dilanni R. Jacobs D

\\

h\\

8109290354 810925 PDR ADOCK 05000289 o

PDR Metropohtan Edison Company is a Member of the General Pubhc Utikties System

ATTACHMENT 1 1.

In our submittal of October 26, 1979 (GQL 1357) Table D-1 lists the parameters to be tested and Table D-2 lists our frequency of pump tests and exceptions to the ASME XI requirements. Revised pages to Table D-1 (Attachment 2) and Table D-2 (Attachment 3) reflects our request for relief from measuring the river water pump flow rate during-the pumps' quarterly test.

Note 12 of Table D-2 provides the basis of the request for relief.

2.

Met-Ed letter GQL 1357 requested relief from the measurement of4P and Pi for spent fuel pumps, SF-PlA/B. The request for relief was not addressed in either Table 2.1 or 2.2 of the SER for Amendment No. 71.

We again request relief from this requirement.

3.

Met-Ed letter GQL 1357 requested relief for Chemical Addition pumps CA-P1A/B; parameters Q, 4P and Pi and Tb.

We understand that this request is being addressed by the inclusion of these pumps in item A.2 of Table 2.2 of the subject SER.

4.

To clarify Section 4.1.7 of the SER, Met-Ed letter dated January 31, 1980 (TLL 032) indicated that there are some category A&B valves which can and are part stroke tested. This does not, however, negate the need for the relief granted for those valves which cannot be part stroked.

4 4

l l

l

{

l

- (!, *

i. '

1,

^

s.

g ';

g g'

n n'

n i

h L

g '

i i

g g

g r

A n

r r

n n

n u

l 1*

V t$;

u**

u i

i i

D f,'t

'r r

Di

.D r

r r

t g f yT

, D ' n 'r-.

.,i u

u u

yn

.'a lh i

a E,

t y'n e "

. yn -

Dn,

D n D n b o,'.

"..ts. !',p' i

g

. o-l o t'

l o o

o o

ri l

e l

I

, 'y i ri ri yi yi yi et if Nt ha.

h a t a 7, y

.,Q y l a 3,

' et et 1 t l t lt

[

rr t

,i s

h t a

,l s.t a.

.bn e "l pn e

,. dhQ@

'.t r t r rx t r rr ri r

i

? ne' ne i e r

C'/ fo,4k,. r

.C r

ol

+

i

.t l p u pt '

o pI

' o p; op-fO t

l

u. q p

.'o MO Qo

. Q, O

'f MO

• MO MO

'r-

.r i

{',

]

'i,' ;

9'. o

,4'.

ffpl.

f'

,1 '

i.

1

'e d

i.,'. f g'

S

- b t.

,- X, h'. li.b i. 'X

[ l'.., i..,/.

X

,h f

.c*.,'

\\

u T

P

2 8

l f

T D

i :.

< Xl X,

X X

N E h.

X~

.E l

.M lU l'

)

l l

'. A G

C A

T E

t T, M

V X

. X X

X X

s

<A i

l E

I T

Q X

X X

IT 7'. '

N

't A

P X

X~

X X

A X. '

X'.

j i,,

I

t S

'Q P.

.,h M.

M N

f U

3 L '..

P.

T i

X X

X X

X X

I O

s.W P

,I

.T

.I M.

.N A.

N X

.U iG 1

l

)

'.NI 0

t D

i A P L

E S N L I O B 1.

1 1

1 1

1 1

I A

G N

N N

N N

N N

-.E T T N

G -

L

('

2 0

2 G

G G

G C

G 4

t i pL d I

- i' 9

9 i

W 8

I E yA 1

0 0

l 0

1 0

M PS 3i 0

0 0

O 0

0 0

G l

E N 1 D E

0 0

0 0

0 0

0 I

E I,.-

l E

0 0

0 0

0 0

0 T

l R

e. l 3

3 3

3 3

3 3

I iT C T

I N

Q

• g, d,,.

A l

.I U

.)

d;

+ i Q

,yN,."

M 1

2 0

2 T

j

)'

3 A

0 1

1 Qf',f q [1 f R 3 -

8 8

6 0

1 0

t i

gG 6

0 0

6 2

6 2

i A

Te dj ;:,.

o, I 2

2 2

2 2

2 2

T gpD 0

0 0

0 0

0 0

F l

@b e

. 3.

3 3

3 2

3 3

O g

j, qC.'

C C

C C

C C

N 1

t};j{. ',

4

.'. j IT t

)

I

{'

S N

f bl.

I

.r'f.,

(

F H

D E

E 8

B u

M R

i",] D,.

PP PP P

PPP PPP PPP P P UN AA A 'B A B' c ABc ABc A

l O

t

] 2 22 1

lll l1l l ] l 1 l F

P

3~

I M

l '. '

P SS EE E

MMM NNN NNN lt l

X GCS t

l l

t t U

FF FF F

UiU if l i i l

l N

i G

I E

E N

T D

DE C

CG I

C E

E EN I

I N D

E

{.

A FO FB DO M

ER EI N

V VI L

G il hL T

il NI rE EO u

E N

L T

i l

E YO YU' AT GT GO u 'C M

l P

U CM CT A

A C

G M

F N(

N(

PC RW lt i

NG A

l U

E

)

E

)

I A

AD GEN I

I P

T Gl E GHE F

El E. l: H TGI E

t l

l L

E EV GEV EI LE E

i t

t l

N l

i E

lETI 1

TI K1 CV CGY AE0 S

1 1 l 4 Tl AJ I

I l

LA EM0

TillWE MII,E ISLAN!' - UNIT NO.1 ATTACllMENT 3 INSEHVICE 3HSPECTION PROCllAM - PUMPS Page 1 of 2 EXCEL'I'[ONS TO ASME XI IWQtlIHEMENTS

=

TAlli,E D-2 Page 1 of 3 ASME XI ASMI. IIi ASME XI EXCEPTION TFSTING PEiWG:Et7s.

PUMP NAME PUMP NO.

CODE CLASS.

CODE CLASS lWQtlESTED "

JUSTIFICATION LIEU 01' CODE N'NilT!W.'EN PACTOli ILUII. DING Hll-P1A 3

Non-Nuclear V

See Note 1 Motor Vibration will be FIEllGENCY COOLING measured Tb See Note 2 None llit-PIB Lubr. Level See Note 2 None Monthly Testing.

See Note 10 Quarterly Tecting Q

See Note 12 Qwillbemeasuredduringred fueling outages.

CIWEN WASil SW-PlA 3

Hon-Nuclear Q

See Note "(

Visual Obneryntion of Flow SW-PIB V

See Note 1 Mot.or Vibration will be men.%

Tb See Note 2 None Lubr. Icvel See Note 2 None CIGEN 110113E SW-P2A 3

Non-Nuclear Q

See Note 3 None.

1:NTILATION SW-P211 V

See Note 1 Motor Vibration will be rucas

,QUIPMENT Tb See Note 2 None Lubr. Level See Note 2 None

__,.,,,s.

ONTil0L hilII. DING All-P3A 3

Non-Nuclear Q

See Note 3 flone.

llII. LED WATER All-P3B Tb See Note 5 None lifAY llEAT DR-P1A 3

Non-Nucl ear V

See Note 1 Motor Vibration will be s.;eas

>lVFH WATEli DH-PlB T

See Not,e 2 None b

Lubr. Level See Note 2 None iPENT FllMf, SI'- Pl A 3

N-3 J'1 See Note la Pi vill be calculut.eu See Note la Hone SF-P1B T

See Note 5 None b

~

dSec ASME SecLion XI for Defia.ition of, Test Quant,it,len i

A

ATTACHMENT 3 Page 2 of 2 Mote 31 The Boric Acid Pumps will be tested only during refueling outages since the only method of testing these. pumps is to inject concentrated boric acid into.

the Reactor Coolant Makeup System. This would adversely affect plant operations and results in additional significant volumes of radioactive waste.

Note 12 The Reactor Building Cooling Water Pumps (RR-PIA /B) supply river water to the Reactor Building Emergency Cooling Coils. These pumps will be tested during normal plant operations using a fixed resistance flow path that bypasses the Cooling Coils. This test will not measure flow rate.

The testing during normal plant operations will not. pump river water through the Cooling Coils because after the test, the Cooling coils must be drained and then flushed with Nuclear Service Closed Cooling Water.

The drain and flush water is drained to the Reactor Building Sump and this produces large quantities of water that must be processed through the Liquid Waste Disposal System. However, flow rate will be measured during refueling outages, when river water is pinped through the Cooling Coils in accordance with Technical Specification-requirements.

I h

,w--,-c..,..,.e,--w,_w.,-y--.r.-e..w,.-,

-w-#,rrw v-wr m, -

w.w e-,--we,..-yww,,