ML19312B888

From kanterella
Jump to navigation Jump to search
Forwards Proposed Tech Specs 3.17,4.19 & 6.1 Re Fire Protection Sys
ML19312B888
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 07/18/1977
From: Parker W
DUKE POWER CO.
To: Case E
Office of Nuclear Reactor Regulation
Shared Package
ML19312B889 List:
References
NUDOCS 7911250078
Download: ML19312B888 (4)


Text

-

u.S. NUCLEAR REGULAToOY J MISSloN cock T NUM BE'l NRC ponu 195

'" h h 2

(

  1. 2 76)

-[NRC DISTRIBUTION pon PART 50 DOCKET MATERIAL FROM:

DATE op ooCUMENT TO Mr. E. Case Duke Power Co.

Charlotte, NC 28242 7 19 77 oATE RECElvEo W. O. Parker 7-20-77

~ KETTE m h7onizEo pace iseuTaceu NuusEn on COnlES RECEIVEo ciNAL MCLAsSinit o gj C C "' '" ltr notarized 7-18-77 trans the Lic. No. DPR-39,47 C 55 Appl for Amend EscLoSw E following:

3P tech specs proposed change concerning revised c addl pages to Fire Protection System....

(1 cy encl rec'd) 9P

,-3-,

-wm bh 2~.I s

I PLANT NAME:

Oconee Units 1-2-3 DHL 7-21-77 CAFE iar FOR ACTION /INFORMATION ENVIPSNMENTAL i ASSIGNED ADr f

1 ASSIGNED AD:

V. MOORE (LTR)

\\ BRANCH CHIEF:

/ noANCH cvTEFr l C

/n I

PROJECT v.ANAGER:

I dCN.d t/lCf.V (

)

) PROJECT MANAGER:

I LICENSING ASSISTANT: I

~ LICENSING ASSISTANT:

l B. HARLESS I

I[

]

INTERNAL DISTRIBUTICN

{ wen eTies /

SYSTZMS SAFET(

l PLANT SYSTEMS SITE SAFETI &

HEINEMAN ITEDESCO ENVIRON ANALYSIS V - _

_u, IT l iSCHROEDER

{BENAROYA DEN"'ON & MULLER MT 2,

e M orta I

ifATNA9 CRitTr urtet n I l COSSICK 8,

STAFT l ENGINEERING lIPPOLITO I

I /41Ma t tr7 I VNTCHT IF. ROSA ENVIRO TECH.

I ivvoc I 20SNAK I

ERNST I 4 race

  • ^1 SIHLELL

! l OPERATING REAC'1DRS BALLARD IonYn VA%'LICvT I

STFT T O YOUNGELOOD I

If ET crNu!t-'

I D90.??rT MANACET' TNT 9CACTOR SAFETI V

SHAO

" ~ ~ "

  • I evnvunt?

ROSS If 3AER I o. CofLTN9 NOVAK If BUTLER GAMMILL (2)

! unecTN ROSZTOCZY I M GRIMES IurtT2

/ CHECK SITH ANALYSIS

!uELTrvrS l

VOLLvJR I cv ATSI l

. BUNCH SALTZMAN I

1[I J. COLLINS I

R"*?E7G I

I IKREGER

// //

yEXTERNAL DISTalBUTION CONTROL NUMBER If LPDRt W W A ",

i f~

c.

V TIC /'

If NSIC I

i i NAT th I

i

/r, 772020036

/

i EIG IV (J. HANCHET~)i i M2 l

l l 7 01i n,,

> De n-

,/

,' /15 CTS ACRS SENT CATIGCRY

- ~.m. Kw a o

{O

(""'

v i

i l s NCC po AM 195(2 76)

[

Duxe POWER COMPANY Powra Butt.DtNo 4e2 SocTu Cucacu STseer CnAnt.oTTz N. C. asa4a c. c..e., i. e.,c.

wf LLI AM O. PA R R E R, J R, July 18,1977 oc, P.c..oc.

L 'ta a PeOOwCCO*e

.h "

N g,((g:@ 'y,/l $s

- s g

Mr. Edson G. Case, Acting Director Of fice of Nuclear Reactor Regulation g

,,}.

~

U. S. Nuclear Regulatory Commission f.

Washington, D.C.

20555

';. J

- 8 LU

'l JUL 2 O1977*s.--

l--

Attention:

Mr. A. Schwencer, Chief U.s. % $

O

'*E Operating Reactors Branch No. 1 OW 6

Reference:

Oconee Nuclear Station JlD.

Docket Nos.

50-269, -270, -287

[bgut,ateg' MA-[b

Dear Sir:

our letter of March 1, 1977, transmitted revisions to the Oconee Nuclear Station These Technical Specifications concerning the present Fire Protection System.

revisions were proposed as requested by your letters of September 28, 1976 and By your letter dated June 17, 1977, revised sample Technical December 1, 1976.

Specifications were provided and an update of our proposed Technical Specifi-cations on the Fire Protection System based on this sample was requested.

In response to this letter and pursuant to the provisions of 10CFR50.90, the attached Technical Specification revisions are requested in lieu of our March 1, It is considered that these specifications will provide assurance 1977 submittal.

of the proper operation of the Oconee Nuclear Station Fire Protection System while Deviations of these permitting the necessary flexibility of station operation.

proposed Technical Specifications f rom the sample Technical Specifications pro-vided by your June 17, 1977 letter are noted in the following discussion.

The fire detection instrumentation at Oconee Nuclear Station does not provide for channel calibration while installed. The instrumentation is calibrated by the manufacturer prior to installation.

Periodic testing assures that the detectors remain sensitive to smoke. Inoperable detectors will be replaced or repaired.

Water is supplied to the two high pressure service water (HPSW) pumps from the Condenaar Circulating Water System piping.

Intake for this water is through the Even if power is twelve pumps located at the intake structure on Lake Keowee.

lost to the CCW pumps, the system can continue to function as a syphon and water In view of the more than ade-would be available to the fire protection system.

quate clean water supply from Lake Keowee feeding directly to the Fire Suppression Water System, Technical Specification requirements for separate water supplies, system flush and verification of water supply volume are considered unnecessary.

77202003S

~

Mr.,Edson G. Case, Act.ag Director Office of Nuclear Reactor Regulation Page 2 l

Present NFPA requirements to assure that sectionalizing control or isolation

~

valves in the Fire Protection System are operable include a weekly inspection of these valves.

The inspection verifies that valves are in their proper position, are sealed adequately, are in good operative condition, turn easily, do not leak, and are readily accessible.

Fire Protection System valves will be tested to these standards.

It is felt that this weekly inspection is adequate to assure that these valves are properly aligned and operable, and therefore, these valves will continue to be tested weekly in lieu of the sample Technical Specifications 4.7.ll.l.c and 4.7.ll.2.a.

't

]

The cprinkler systems in safety related areas at Oconee Nuclear Station are presently tested yearly by actuating the system and verifying water flew through the sprinkler heads.

It is felt that this method of testing is superior to a test using air to verify that no blockage exists as stated in sample Technical j

Specification 4.7.11.2.c.

Therefore, this system will continue to be tested i

utilizing a " wet test".

Monthly verification of the operability of each fire hose station will con-sist of a thorough visual inspection.

Fire hose stations do not have individual standpipe pressure indicators.

i Performance of a local leakage test for penetration fire barriers that perform a pressure sealing function is not possible due to the inaccessibility of pene-trations and the inability to establish a functional sealed test area around penetrations.

Penetration fire barriers that perform a pressure sealing function are located only in the penetration room.

A yearly test to verify a slight negative pressure in the penetration room is already performed.

It is felt that this test and the thorough visual inspection of fire penetrations barriers after maintenance or modifications will adequately assure the integrity of these barriers.

V ytrulyyours,{

w' c0 I

William O. Parker, J.

LBJ:rr Attachment d

4 i

~

July 18, 1977 Page 3 WILLIMI 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company 4

to sign and file with the Nuclear Regulatory Commission this request for 4

,l amendment of the Oconee Nuclear Station Facility Operating Licenses DPR-38, DPR-47, and DPR-35; and that all state =ents and =atters set forth therein are true and correct to the best of his knowledge.

r Wa (A e

i l

Willias 0. Parker, Jr., J/ce President i

Subscribed and sworn to before se this 1Sch day of July,1977.

M 1

Notary Publa.c My Cecoission Expires:

d. /$ /Yf2-l i

l

"