ML20215L907

Responds to Generic Ltr 86-06 Re Testing Requirements for Pressure Isolation Valves in Rcpb.Tech Specs & Implementation of Inservice Testing Program in Conjunction W/Leakage Detection Capabilities Assures Integrity of RCPB

ML20215L907
Person / Time
Site:	Oyster Creek
Issue date:	06/18/1987
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Murley T Office of Nuclear Reactor Regulation
References
GL-86-06, GL-86-6, NUDOCS 8706260211
Download: ML20215L907 (3)

Text

]

i J

o O

ENuclear

==:r 388 1

GPU Nuclear Corporation Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

June 18,1987 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission a'

Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Generic Letter 87-06 Generic Letter 87-06 requests information pertaining to testing requirements for all pressure isolation valves (PIVs) within the reactor coolant pressure I

Soundary.

The requested information is provided in accordance with 10 CFR 50.54(f).

The Technical Specifications for the Oyster Creek plant were amended in accordance with the NRC Event V Order dated April 20, 1981.

This order included pressure isolation valves for Core Spray Systems I and II.

In.accordance with Generic Letter 87-06 a review of the reactor coolant pressure boundary (see attached drawing) was made to identify any other valves which perform a pressure isolation function.

Except for the Core Spray System, all other systems connected to the reactor coolant pressure boundary are designed to withstand reactor coolant system pressure at the reactor coolant system pressure boundary interface.

These systems are as follows:

1.

Main Steam (PIVs open during operation) 2.

Emergency Condensers (Isolation Condensers) 3.

Feedwater (PIVs open during operation) 4.

Reactor Cleanup (PIVs open during operation) 5.

Control Rod Drive 6.

Coolant Sampling 7.

Shutdown Cooling 8.

Liquid Poison i

9.

Reactor Head Cooling 10.

Hydraulic Instrumentation (1" lines or less) (0 pen during operation)

The above listing does not include the electromatic relief valves (EMRVs),

main steam safety valves, or the reactor head vent...The EMRVs and the main-steam safety valves discharge to the suppression chamber and the drywell, respectively.

Leakage through these valves can be detected by ' temperature and acoustic monitors.

The reactor head vent discharges to the main steam line upstream of the main steam isolation valves.-

A > branch. line vents to the drywell equipment drain tank through two isolation valves.

Leakage -through

'hese valves would be indicated by an increase in the identified leak rate.

8706260211 870618 gl/0 PDR ADOCK 05000219

'f I(

p PDR Gt --...-. uvipuianuiiis o suudiusaty ut tne General Public Utilities Corporation ii

Upon exceeding a total (identified plus unidentified) leak rate of 25 GPM corrective action must be taken within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or the reactor must be shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and be in cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The Inservice Testing Program for the Oyster Creek Station provides a description of those isolation valves performing a pressure isolation function within systems connected to the reactor coolant pressure boundary (i.e.,

cleanup system demineralizer, main feedwater, control rod drive hydraulic system).

Section 4.3 of the Oyster Creek Technical Specifications require testing in accordance with this program which has been submitted to the NRC by letter dated March 12, 1987.

GPUN believes the existing Technical Specifications with regard to the Core Spray System and implementation of the Inservice Testing Program in conjunction with leakage detection capabilities assure the integrity of the reactor coolant pressure ~ooundary.

If you should have any questions please contact Mr. George Busch, OC Licensing Engineer at (609)971-4909.

Very truly yours, e-

^

t fedler Vice President and Director Oyster Creek Sworn to and Subscribed o

8 o

L k.AElms D!ANA M. DeBLASIO NOTARY PUBUC OF NEW JESSEY My Commission Expiree 6/5/f/

PBF/GB/dmd(0144A)

Attachment

-l cc: Mr. William T. Russell, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projects I/II 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station

• *,, 3r I

l, l

l lij l8 11 1 l l g1 Illi i a, l, l,1, I $

1..

.a 1

3 IZ.&,A.

ilr

• q -

g s in s

..{e.

e,.d g =1 13 13 2 h 1

t

....i;!.e Ji...

J e.i:

n a.

sf s :d

. q...,.... ; a n.r

!Lt a

.......f.,.

2 7!:

I l

E i' i

!S l

E" gg l

n f1 l

i a

tv l

~

Il 8

I I

l fl E

s I

e o

I i

i a-,-

s i

er i

l

! I l l

m i,

s~ -

3 f

j

-l 8

a i

i+

l o

m a

/

l 1,

//

.1 l

8 :

o i

i

/

li:

l

/'

.p~ :

l 1

3 P-8

~-

3 Ir i l!

l fil ilf t p l,[i I:

~q

. nJ e

l

(

11 l

1 l

u

>I l

I l

1 N

l s

l s

]+

l l

1 o

_CJ l-I

[

u l

5 g

a o

i

~

.Z in i

~

l i

8 B-.

l l

o o

l i.

I i

g e

e g

l i

e e

I l

)

1 I

E i

~

i i

s g

d I

)

e o

lZ 3

a

s...

l D

i e,

y z

l e

e a F

n; l

1

....."I

..I

$7 T

a s" a

.j.. i!.. Ca..

... r-cg...?..i.... _ j

$2!

Fj[7f !h

!jh 1

h' j

h GPU NUCLEAR CORPORATION OYSTER CREEK NUCLEAR GENERATING STATION REACTOR COOLANT SYSTEM BOUNDARlEO UPDATED FINAL SAFETY ANALYSIS REPORT REV. O,12/84 l

FIGURE 5.21

.