ML18010A870

Forwards Documentation Re Mod to HHSI Alternate mini-flow Sys,Per 921007 Meeting W/Nrc & as Suppl to 921009 & 12 Submittals

ML18010A870
Person / Time
Site:	Harris
Issue date:	10/28/1992
From:	Mccarthy D CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLS-92-293, NUDOCS 9211050162
Download: ML18010A870 (6)

Text

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ACCESS.'ON iNBR: 9211050162 DOC. DATE: 92/10/28 NOTARIZED: NO DOCKET FACIE+50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION MCCARTHY,D.C. Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Forwards documentation re mod to HHSI alternate mini-flow sys,per 921007 meeting w/NRC & as suppl to 921009 & 12 submit tais.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed. 05000400

/

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD2-1 LA 1 1 PD2-1 PD 1 1 LEFN 2 2 INTERNAL: ACRS 6 6 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 1 OC 1 0 OGC/HDS1 1 0 RE IL 01 1 1 RES/DSIR/EIB 1 1'-

N EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK.

ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 22 ENCL 20

CNK Carolina Power 8 Light Company OCT 88 199P.

SERIAL: NLS-92-293 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 HIGH HEAD SAFETY INJECTION ALTERNATE MINI-FLOW (AMF) SYSTEM MODIFICATION Gentlemen:

As a result of the meeting on October 7, 1992 between Carolina Power & Light Company (CP&L) and the NRC Staff on the modification to the Shearon Harris Nuclear Power Plant (SHNPP) High Head Safety Injection AMF System, the NRC Staff requested that CP&L submit documentation regarding the modification's design, supporting calculations, and testing for NRC review. By letters dated October 9, 1992 and October 12, 1992, CP&L provided the requested information.

Since that, time, via the NRC Project Manager, we have responded to questions posed by the NRC's technical reviewers. In the course of responding to the additional questions, CP&L has been asked to provide written responses to three specific items. Carolina Power & Light Company's responses to these items are included as Enclosure 1 to this letter.

Carolina Power & Light Company understands that the NRC Staff has no additional questions related to the planned system modification at this time.

Should you have any questions concerning the information in Enclosure 1, please contact me at (919) 546-6901.

Davi C. McCarthy Manager Nuclear Licensing Section LSR/j bw Enclosure cc: Mr. S. D. Ebneter Mr. N. B. Le Mr. J. E. Tedrow 92ii050i62 9'2i028 PDR P

• DOCK 05000400 PDR L'1812HHP)

,~ tevilte Street e P. O. Box 1551 o Raleigh. N. C. 27602

ENCLOS 0 SERIAL: NLS-92-293 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NO. NPF-63 HIGH HEAD SAFETY INJECTION ALTERNATE MINI-FLOW (AMF) SYSTEM MODIFICATION Item 1:

As a result of this AMF System modification, confirm that the resultant flow rates to the Reactor Coolant System continue to meet or exceed the assumptions for the FSAR Chapter 15 Small Break LOCA analysis.

CP&L Res onse:

The as-modified High Head Safety Injection AMF System will continue to provide flow that bounds the flow assumed in the FSAR Chapter 15 analyses.

Item 2:

How does CP&L intend to periodically test the High Head Safety Injection AMF System?

CP&L Res onse:

The Reactor Coolant System (RCS) pressure inputs which actuate the AMF valves coincident with safety injection will be checked with the other safety injection channels per the guidance of Technical Specification Table 4.3-2.

This includes a channel check once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an analog channel operational test once per month, and a channel calibration once per 18 months. A verification of the AMF valve interlock action will be performed once per 18 months as a portion of the testing included in Technical Specification surveillance requirement 4.5.2.e. If the RCS pressure coincident with safety injection is inoperable, CP&L will declare the associated AMF isolation valve and pump inoperable and will comply with the action specified in Technical Specification 3.5.2 or 3.5.3, as appropriate. This testing will be accomplished through Operations Surveillance Tests (OST) and Maintenance Surveillance Tests (MST).

Item 3:

Does CP&L plan to revise any procedures and conduct training on the modification to the AMF System?

CP&L Res onse:

Procedural changes required to implement the AMF System modification have been identified, and required changes will be incorporated prior to plant startup.

Operators will be trained on the revised AMF System design and operation prior to plant startup.

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