ML18230A771

Letter Amendment No. 41 to Preliminary Safety Analysis Report

ML18230A771
Person / Time
Site:	Harris
Issue date:	05/05/1975
From:	Jackie Jones Carolina Power & Light Co
To:	Rusche B Office of Nuclear Reactor Regulation
References
Download: ML18230A771 (6)

Text

NRC I RIBUTION FOR PART 50 DOCKE

. ATERIAL (TEMPORARY fORM)

CONTROL NO:

5022 FILE'ROM.

Carolina Power & Light C

Raleigh, N.C.

7 A Jones 5-5-75 Sri 5 "7-75 XX

'DATE OF DOC DATE REC'D LTR TWX RPT OTHER TO:

Hr. Benard C.

Rusche CLASS UNCLASS PROPINFO XXXX DESCRIPTION ORIG 1-signed INPUT CC OTHER NO CYS REC'D 25 ENCLOSURES:

SENT AEC PDR xxxx SENT l OCAL PDR xxx OCKET NO:

50-40, 401, 402, and 403 Ltr notarized 5-5-75 furn their position on the"Preoperational Testing of Emergency Core Cooling Syst:ems for Pressuri'zed Water Reactors"

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PLANT NAME Shearon Harris 1-4 FOR ACTION/INFORMATION UTLER (L)

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WIGG I NTON R. INGRAM ILI LOCALPDR Raleigh, N.C..

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CÃQD, Carolina Power & Light Company May 5, 1975 4

Mr. Benard C. Rusche, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555

+&AI RE:

DOCKET NOS. 50-400 50-401 50-402 and 50-403

Dear Mr. Rusche:

On March 24, 1975,'Carolina Power 6 Light Company submitted Amendment Number 41 to the Shearon Harris Nuclear Power Plant PSAR.

In this amendment, we provided our company positions on regulatory, guides issued through July 1974.

We also committed to submit our position on Regulatory Guide 1.79, "Preoperational Testing of Emergency Core Cooling Systems for Pressurized Wat:er Reactors,"

as soon as Ebasco Services and Westinghouse had completed their evaluation.

Our position is as follows:

The SHNPP Project will comply with Regulatory Guide 1.79 (6-74),

"Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors," with the following clarifications/

excepeions:

Re

. Position C.3.a.(2)

Clarifications/Exce tions The capability of the HPSI to deliver as required under accident conditions will be verified by analysis based on as-built HPSI pump and system head-capacity curves.

Operation of the check valves and the auxiliary feedwater system will be demonstrated through testing.

C.3.b. (2)

The capability to realign valves for recirculation will be tested for all SHNPP units.

Tests of the system to demonstrate vortex control in the RHR sump, acceptable pressure drops across screening and suction lines and valves, and adequate NPSH will be conducted for Unit 1 only and referenced for the remaining units.

However, if LPSI recir-culation tests are conducted in other plants with similar sumps and/or RHR systems prior to SHNPP preoperational testing, those tests may be referenced in lieu of testing SHNPP Unit l.

r>+pal 336 Fayetteville Street

~ P. O. Box 1551

~ Raleigh, N. C. 27602

I' L'

Mr'.

enard.C. Rusche C.3.c.(l)

Blowdown will be into the open reactor vessel at ambient pressure.

This condition will allow the rapid accumulator dump which is necessary for evaluation of the system performance.

Proper initiation of accu-mulator dump will be demonstrated by testing the accumulator check valves as described in Regulatory Position C.3.c.(3).

C.3.c. (3)

Initial RCS pressure for this test will be greater than the normal accumulator precharge pressure but less than the normal RCS operating pressure.

C.4.b. (3)

Maximum expected temperature is taken to mean the normal operating temperature.

Carolina Power

& Light Company will change its PSAR to reflect the above regulatory guide position in its next amendment.

urs very truly, J. A. Jones Executive Vice President Engineering, Construction

& Operation JAJ/nc/apl J. L. Lancaster,CJr.

Secretary Sworn to and subscribed before me this 5th day of May, 1975.

My Coinmission Expires: P+ +/~

LM N'ary Public

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