ML18019A593

Forwards Addl Info Re Surveillance Testing of RCPB Isolation Valves,Per 851203 Meeting.Changes Made to 830930 Commitments to Reflect Draft Rev 5 to NUREG-0452.Proposed FSAR Page 3.9.6-2 Also Encl

ML18019A593
Person / Time
Site:	Harris
Issue date:	02/20/1986
From:	Zimmerman S CAROLINA POWER & LIGHT CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-NUREG-0452, RTR-NUREG-452 NLS-86-029, NLS-86-29, NUDOCS 8602260204
Download: ML18019A593 (7)

Text

\\

~s

SUBJECT:

Forwards addi info re surveillance testing of RCPB isolation valves> per 851203 meeting. Changes made to 830930 commitments to reflect draft Rev 5 to NUREQ-0452. Proposed FSAR Page

3. 9. 6-2 also encl.

DISTRIBUTION CODE:

B001D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: Licensing Submittal:

PSAR/FSAR Amdts 0 Related Correspondence NOTES:

REGULATO INFORNATION DISTRIBUTION TEN (RIDS)

ACCESSION NBR: 8602260204 DOC. DATE: 8h/02/20 NOTARIZED:

NO FACIL:50-400 Shearon Harris Nuclear Power Planti Unit 1> Carolina AUTH. NANE AUTHOR AFFILIATION Z.INNERMANiS. R.

Carolina Power Zc Light Co.

RECIP. NAME RECIPIENT AFFILIATION DENTONi H. R.

Office of, Nuclear Reactor Regulation>

Director (post 851125 h

RECIPIENT ID CODE/NANE PMR-A ADTS PMR-A EB PMR-A FQB BUCKLEY> B 01 PMR-A RSB INTERNAL: ADM/LFNB IE FILE IE/DGAVT/GAB 21 NRR PMR-A ADTS NRR RQE> M. L NRR/DHFT/NTB NRR/DSRO/RRAB RGN2 EXTERNAL: 24X DNB/DSS (ANDTS)

NRC PDR 02

'NL GRUEL' COPIES LTTR ENCL 1

1 1

1 1

2 2

1 1

0 1

1 1

1 0

1 1

1 1

1 1

3 3

1 1

1 1

1 RECIPIENT ID CODE/NANE

PMR-A PD2 PD

PMR-;A EICSB

PMR'-"* PD2 LA

,PMR-:* PSB

,ELD'/HDS1 IE/DEPER/EPB 36

'.NRR BMR ADTS

NRR.PMR-B ADTS NRR/DHFT/HFIB S

DIR 04

RN/DDANI/NIB BNL(ANDTS ONLY)

LPDR 03

'NSI C 05 COPIES LTTR ENCL 1

1 1

1 1

1 1

1 0

1 1

1 0

1 0

1 1

1, 0

1 1

0 1

1 1

1 1

TOTAL NUNBER OF COPIES REQUIRED:

LTTR 35 ENCL 28

(pr>>

lj'jlj "i'

.'f ", P(

1."jrj

(>>

S p) Ij Iij>>,. i; >>'lI,I

~

.1

-'.'WP<< if'(W'j>>P'

'I4 f

,>>j ]

I jl>>r)<<

I ~

"C>> TIi>>

,i, P,f>>>>'P<

> ~ I <<W f jr ~ <<>>;p g p I >> j'< (I )'>> ~". ~ II III >>Nf >>)<< lf 4,)>> I WW W IP C.'P .'a<<t 4>> ~ i.'">> r ." 4" 8 <'1 W t<< ~ - "i>>,W","4 CW>> '.;.<>> > 8 jt~jj.-a>>:,I 'p,! n,'("' ". j >.=,> qf." > pry(p ) jf>>ps It j'>> cj. Ig ) I I jp rp>>wIp q>>s'wl<> > (( 'l SW 'f Q>> C'I P 1 'Pr IW I >>P' . jj I>>PI 11I ~ W I S>>f W .i>>j', 1I ~, 'll fj I j>>fjr Il Ps>>S,>>(1 P CS,,'rg I l >>PI 'rf I ll,f'.l )>>," j .f"',,<>x~ 1>> I, W <<Pl >>, II ~" I W I I'I ( jf>> S 1 P W >>1 II I If"Cp 1 ~ Qrg I Carolina power S Light Company FEB 8 0 >9SG SERIAL: NLS-86-029 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO. 1 - DOCKET NO.50-000 PRESSURE ISOLATION VALVETESTING

Dear Mr. Denton:

Carolina Power R Light Company (CPdcL) hereby submits additional information concerning surveillance testing of reactor coolant pressure boundary isolation valves.

This information updates commitments made in CPRL letter to Mr. H. R.

Denton (LAP-.83-007) dated September 30,

1983, and reflects agreements reached in a

December 3, 1985, meeting with the NRC Staff.

The changes to CPRLrs previous commitments are being made to reflect draft Revision 5 of the Westinghouse Standard Technical Specifications (NUREG-0052) with the exception of the RHR System suction valves.

The proposed changes and justification for the exception are shown on the attached mark-up of FSAR Page 3.9.6-2, which will be included in a future FSAR amendment.

Technical Specification 3/0.6.2 willalso reflect this change.

If you have any questions on this subject, please contact Mr. 3. D. Kloosterman at (919) 836-8055.

Yours very truly, 3DK/Ijs (32783DK)

S.. Zi merman anager Nuclear Licensing Section CC:

Mr. B. C. Buckley (NRC)

Mr. G. F. Maxwell (NRC-SHNPP)

Dr. 3. Nelson Grace (NRC-RII)

Mr.'ravis Payne (KUDZU)

Mr. Daniel F. Read (CHANGE/ELP)

Mr. Wells Eddleman Wake County Public Library 8602260204 860218 PDR ADOCN, 05000488 P

PDR Mr. O. O. Rothberg (NRC-MEB)

Mr. 3ohn D. Runkle Dr. Richard D. Wilson Mr. G. O. Bright (ASLB)

Dr. 3. H. Carpenter (ASLB)

Mr. j. L. Kelley (ASLB)

Mr. H. A. Cole 411 Fayettevilte Street

~ P. O. Box 1551

~ Raleigh. N. C. 27602

,o/

'l

<<'> Pt

<3 ~ 8>"

.I

SHNPP FSAR dry 748 There are several safety systems connected to the reactor cooLant pressure boundary that have design pressures that are below the reactor coolant system operating 'pressure.

Redundant isolation valves, forming the interface between these high-and-low-pressure

systems, have been provided to prevent the low pressure systems from being subjected to pressures which exceed their design Limits.

In this roLe, the valves are performing a pressure isolation function.

Carolina Power

& Light Company will provide assurance that the condition of each of these valves is adequate to maintain this redundant isolation and system integrity.

Leak testing will be used to assure their condition is sufficient to maintain this pressure isoLation function.

Valves categorized as'A or AC, which do not function in the course of pLant operation in a manner that demonstrates'functionally adequate seat tightness, are Leak tested in accordance with IWV"3420 of Section XI of the appLicable edition of the ASME Code.

alves designated as Category A (or combination of categories such as Category AC) will be tested to verify leakage is Less than l gpm at-2235

+20 psig when pressurized individually.

Testing will be perfo med o the following schedu e:

a)

At Least once per 18 months.

b)

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.

I c)

Prior to returning the valve to service following maintenance, repair or replacement vork on the valve.

d)

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Eollowing actuation due to automatic or manual action or flow through the valve.

The inservice valve test program.clearly identifies which vaLves are applicable to the above position.

The SHNPP valve test program Lists aLL valves (except those used Eor operating convenience only, such as manuaL vent, drain, instrument, and test valves; controL valves; thermal reL'ief valvese and valves used only Eor maintenance) that are subject to testing and indicate the test parameters to be measured.

The valve program tables are arranged in order by Flow Diagram number.

3.9.6.3 Relief Re uests 23 Requests Eor reLief from ASME Section XI requirements are submitted in the Pump and Valve Test Program.

Lnformation provided describes the specific area oE relief requested, explains

~hy compliance with Section XI is impracticaL, and describes alternative test procedures.

A continuing program of radiation surveys during the retueling programs wiLL be performed to ensure that any possible future problem areas are detected at an early stage.

Should addi.'tionaL experience in the maintenance and inspection of operating plants indicate that areas exist where access wiLL be either Limited or impossible, requests Eor relief from'Section XI requirements wilL be made.

3.9.6-2 Amendment No.

23

Reference g 3.9.6.2, page 3.9.6-2 Insert A Valves categorized as A or AC will be tested to verify leakage is less than the following when pressurized individually at 2235 + 20 psig.

For valves up to and including 10 inches nominal valve size:

I/2 gpm per inch of nominal valve size; for valves greater than 10 inches:

5 gpm maximum.

As permitted by paragraph IWV-3023 of Section XI, leakage tests may be performed at lower than 2235 psig for check valves and gate valves.

In such cases the observed leakage shall be adjusted by multiplying the observed leakage by the square root of the quotient of 2235 divided by the test pressure.

Testing will be performed to the following schedule:

Insert B Paragraphs b) and d) directly above willnot apply to the following valves:

IRH-V500SB-I IRH-V501SA-I The justification for this exclusion is as follows:

IRH-V502S8-I IRH-Y503SA-I 1) full closure of these valves is verified in the control room by direct monitoring position indicators, 2) inadvertent opening of these valves is prevented by interlocks which require the primary system pressure to be below subsystem design pressure prior to opening, and 3) gross intersystem leakage into the RHR system would be detected by high-pressure alarms located in the control room.

(3278JDK/I js)