ML15223A481

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Forwards Safety Eval Rept for Subj Facil Re Mod to High Pressure Injection Sys
ML15223A481
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 12/13/1978
From: Reid R
Office of Nuclear Reactor Regulation
To: Parker W
DUKE POWER CO.
Shared Package
ML15223A482 List:
References
NUDOCS 7812260062
Download: ML15223A481 (2)


Text

DI TRIBUTION.

1-focket File (3)

Ga F'

December 13, 1978 NRC PDR. (3F L PDR.(3)

TERA ORB#4 Rdg JRBuchanan

.N BGrimesC%

TJCarter and 50-287 Ringramr MFairtile Attorney, OELD 01&E.(5)

Mr. Wil1Iam-0. Parker, Jr.

Bhones (4)

Vice President -

Power Production Scharf (

Duke Power Company

- H

.BHar,1ess P. 0. Box 2178 Miles, OPA.

422 South Church Street DEisenhut Charlotte, North Carolina 22 AS6s DRosS

Dear Mr. Parker:

By letter dated July 14, 1978 and s upplemented Ngember 6, 1979, Duke Power Company submitted a proppsedmodificat on, t.the High, Pressure Injection System (HPIS) fgyJthe,0cong

.yclear Station, Units Nos. 1, 2 and 3. The modificatign tp-the.system yas required to ensure that the Emergency CoreCooinqg ystem, ofwhich the HPIS is a component, was wholly in-conformance with 10 CFR 5T.46. An error in the ECCS analysis was rought to our attentjon.by Duke,Power Company in their letters of Apri1l14,and ?1,.1978;.,by letter dated May 15, 1978, Duke Power Company. prvided analysisi.to. suppprt continued opyration of the Oconee Station With operator actions neeiced outside the control room. The gly14.GsbmittaI from Duke Power Company proposed a modification.to.-the HPISwhereby-only simple operator action from within the cntrol, roomwas neededtoplace the ECCS wholly in conformance with 10 CFR50.46.

We have found the design modifjcations to the.,fPIS to be acceptable.

-Our review is presented in the epclosedSfety Evaluation Prior to operation of the modifiedHPJS yojiwill needto,subiqjt.a.

license amendment with appropriate survellance technical-specifications for the modified portions of thesystem. After our review of the.

appropriate technical specificatiopswe will perfoirmour.ffinal.review of conformance with 10 CFR 50.6.

78.26

.Sincer0,1Y Robert W. Reid, Chief

  • SEE PREVIOUS YELLOW FOR Operating Reactors Branch CONCURRENCE Division of Operating React s Eclosure:

%.r OFSICE tCvy... Eval.uat on-_.................

ORB#4:DOR 0ELD AD-E&P:DOR C-0RB#4:DOR SURNAME*

Wf-eriosr BGrimeS RReid.

c ATEt 12/t 778 12/12/78.

1 '78.......2/.'8.

NRC FORM 318 (9-76) NRCM 0240 U. S. GOVERNMENT PRINTING OFFICEi 1976 -

625-624

DISTRIBUTION:

Docket File (3)

Gray File NRC PDR (3) 4 Extra Cys L PDR (3)

TERA Dockets Nos.:

50-269 ORB#4 Rdg JRBuchanan 50-270 VStello WOMiller,LFMB and 50-287 BGrimes B TJCarter RIngram MFairtile Attorney, OELD

-Mr. William 0. Parker, Jr.

OIE (5)

Vice President - Steam Produqjqn IBJones (4)

Duke Power Company 13Scharf U 10)

P. 0. Box 2178 STSG 422 South Church Street BHarless Charlotte, North Carolina 2 24 DEisenhift ACRS (16)

Dear Mr. Parker:

OPA, CMiles DRoss By letter-dated July 14, 1978 and as supplemented November 6, 197d, Duke Power Company submitted aproposed, modification to the High Pressure Injection System (

)fo.)rthe Oconee, Nuclear Station.,

Units Nos. 1, 2 and 3. The Igdificatfan to-the system was required to ensure that the Emergencyore Cooling Systev, of which, the HP is-a component, was wholly 1toconformance with 10 CFR 5.46.

An error in the ECCS. analysis.1wa brought to our.attentiort by Duke Power Compai in their letters of April 4an 2l,.198 by letter dated May 15, 1978, Duke Power Comp ny royide analysis to support continued operation of the Oconey SAtion with qperator.actios needed outside the centrol room.. The Jjly,14 subjpittal from Duke Power Company proposed a modificatiq to the HIS, whereby only simple operator action from within athe coptrol room was needed,.to place the ECCS.wholly in conformance with 10 (FR 50.46.

We have found the design modifications tothe HPIS to be.acceptable.

Our review is presented in thg enc1osqjSafety Evaluation.

Sincerely, Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Enclosure:

Safety Evaluation cc w/enclosure; See ne page.

oRB4D0R E

AD P0#D SURNAME MFairtile:r I

RReid DATE..

12/#1/78 12 78 12/3/78 12/3'78 NRC FORM 318 (9-76)

NRCM 0240 U. S. GOVERNMENT PRINTING OFFICE. 1970 - 626*624