ML14183A699

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Informs That Proposed Change to TS Bases Section 4.8 Re Testing of Steam Driven Auxiliary Feedwater Pump for Plant, Acceptable
ML14183A699
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 10/17/1995
From: Mozafari B
NRC (Affiliation Not Assigned)
To: Hinnant C
CAROLINA POWER & LIGHT CO.
References
TAC-M93571, NUDOCS 9510240373
Download: ML14183A699 (3)


Text

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October 17, 95 Mr. C. S. Hinnant, Vice President Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550

SUBJECT:

CHANGE TO TECHNICAL SPECIFICATION BASIS SECTION 4.8 REGARDING TESTING OF THE STEAM DRIVEN AUXILIARY FEEDWATER PUMP FOR THE H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 (TAC NO. M93571)

Dear Mr. Hinnant:

By letter dated June 1, 1995, Carolina Power & Light Company (CP&L) proposed a change to the H. B. Robinson Steam Electric Plant, Unit No. 2 (HBR), Technical Specifications (TS) Basis section 4.8. The Basis change clarifies stable conditions for the surveillance testing of the steam driven auxiliary feedwater pump after a period in which the reactor has been in cold shutdown.

The NRC staff has reviewed the proposed basis change regarding stable plant conditions for conducting surveillance tests on the steam driven auxiliary feedwater pump and has no objection to your proposed change.

Enclosed is a copy of the revised Basis page.

Sincerely, (Original Signed By)

Brenda Mozafari, Project Manager Project Directorate II-I Division of Reactor Projects -

I/II Office of Nuclear Reactor Regulation Docket No. 50-261 Distribution Docket File DVerrelli, RII

Enclosure:

Basis page 4.4-10 PUBLIC PD2-1 RF cc w/enclosure:

See next page SVarga JZwolinski OGC FILENAME -

G:\\ROBINSON\\ROB93571.LTR ACRS (4)

OFFICE LA:PDII-1 P _PDII-1

-1 NAME Dunnington ozafari ews DATE 10/)1/95 4W60//95 10/

/95 COPY Yes No Yes No Yes No OFFICIAL RKGORD COPY 9510240373 951017 PDR ADOCK 05000261 P

PDR

Mr. C. S. Hinnant H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:

Mr. R. E. Jones Mr. Dayne H. Brown, Director General Counsel - Legal Department Department of Environmental, Carolina Power & Light Company Health and Natural Resources Post Office Box 1551 Division of Radiation Protection Raleigh, North Carolina 27602 Post Office Box 27687 Raleigh, North Carolina 27611-7687 Karen E. Long Assistant Attorney General Mr. Robert P. Gruber State of North Carolina Executive Director Post Office Box 629 Public Staff - NCUC Raleigh, North Carolina 27602 Post Office Box 29520 Raleigh, North Carolina 27626-0520 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Max Batavia, Chief H. B. Robinson Steam Electric Plant South Carolina Department of Health 2112 Old Camden Road Bureau of Radiological Health Hartsville, South Carolina 29550 and Environmental Control 2600 Bull Street 4

Regional Administrator, Region II Columbia, South Carolina 29201 U.S. Nuclear Regulatory Commission 101 Marietta St., N.W., Ste. 2900 Mr. J. Cowan Atlanta, Georgia 30323 Manager Nuclear Services and Environmental Mr. Dale E. Young Support Department Plant General Manager Carolina Power & Light Company Carolina Power & Light Company Post Office Box 1551 - Mail 0HS7 H. B. Robinson Steam Electric Plant Raleigh, North Carolina 27602 3581 West Entrance Road Hartsville, South Carolina 29550 Public Service Commission State of South Carolina Post Office Drawer 11649 Columbia, South Carolina 29211 Mr. R. M. Krich Manager - Regulatory Affairs Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, South Carolina 29550

4.8.5 The survd ance requirements for auxilia feedwater system automatic initiation shall be as stated in Table 4.8-1.

Basis The monthly testing of the auxiliary feedwater pumps by recirculation will verify their operability. The capacity of any one of three auxiliary

(,edwater pumps is sufficient to meet decay heat removal requirements,

Proper functioning of the steam turbine admission valve and the starting of the feedwater pumps will demonstrate the integrity of the steam driven pump.

Verification of correct operation will be made both from instrumentation within the control room and direct visual observation of the pumps. Testing of the steam turbine auxiliary feedwater pump is not required during periods of cold shutdown when steam is not available. In this condition the pump is not required for plant safety. If the steam turbine driven auxiliary feedwater pump has exceeded its surveillance interval following a period of reactor cold shutdown, then the surveillance test shall be performed prior to reactor criticality, but not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after the reactor coolant system has been at a minimum 547 deg. F.

References (1) FSAR Section 10.4 (2) FSAR Section 14.1.11 (3) FSAR Section 14.2.5 4.8-2 Amendment No. 59 REVISED BY NRC LETTER DATED October 17, 1995