ML20132F191

Forwards Corrections to 1984 Update to FSAR for McGuire Units 1 & 2,submitted by

ML20132F191
Person / Time
Site:	McGuire, Mcguire
Issue date:	07/16/1985
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8507180327
Download: ML20132F191 (13)

Text

y; DUKE POWER GOMPANY P.O. Box 33180 CHAMLOTTE, N.C. 28242 HALH. TUCKER TELEPHONE July 16, 1985 po4)am 4sm m......

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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Ms. E. G. Adensam, Chief Licensing Branch No. 4

Subject:

McGuire Nuclear Station Docket Nos.

50-369, -370

Dear Sir:

The 1984 update to the McGuire Nuclear Station Final Safety Analysis Report which was transmitted by my letter dated July 1, 1985, contained several administrative errors. Please find attached corrections to the 1984 update.

Very truly yours.

M k - C se:

O Hal B. Tucker WHM:scs Attachments cc: w/o attachment Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission l

Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station 1

Y O

8507100327 050716 l\\-, )g PDR ADOCK 05000369 K

PDR L

r-Mr. Harold R. Denton, Director July 16, 1985 Page 2 HAL B. TUCKER, being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission.this revision to the McGuire Nuclear Station Final Safety Analysis Report and that all statements and matters set forth therein are true and correct to the best of his knowledge.

GW sc Hal B. Tucker, Vice President Subscribed and sworn to before me this 16th day of July, 1985 Notary Public My Commission Expires:

September 20, 1989

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DUKE POWER COMPANY APPLICATION FOR LICENSES DOCKET NO.

50-369 -370 July 16, 1985 McGuire Nuclear Station Final Safety Analysis Report Remove These Pages Insert These Pages Figure (s) 4.2.3-4 Figure (s) 4.2.3-4, 4.2-3-5 Figure (s) 4.2.3-5, 4.2.3-6 Figure (s) 4.2.3-6, 4.2.3-7 Figure (s) 4.2.3-7, 4.2.3-8 Figure (s) 4.2.3-8, 4.2.3-9 Figure (s) 4.2.3-9, 4.3.2-1A Figure (s) 4.3.2-1, 4.3.2-1A Table (s) 6.3.2-2 thru 6.3.2-3A 1 of 2 Table (s) 6.3.2-2, 6.3.2-3A 1 of 2 l

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3 = 4 Tobie 6 .2-2 (^' Normal Operating Status of Emergency Core Coolino System Components for Core Cooling Number of Safety Injection Pumps Operable 2 Number of Charging Pumps Operable 2 Number of Residual Heat Removal Pumps Operable 2 Number of Residual Heat Exchangers Operable 2 Refueling Water Storage Tank Volume, Gal., minimum 372,100 Boron Concentration in Upper Head Injection Surge Tank, minimum ppm 1,900 Boron Concentration in Refueling Water Storage Tanks, minimum ppm 1,900 Boron Concentration in Cold Leg Accumulator, minimum ppm 1,900 Boron Concentration in Upper Head Injection Accumulator, minimum ppm 1,900 Number of Accumulators 6 O 400 Q Minimum Cold Leg Accumulator Pressure, psig Minimum Upper Head Accumulator Pressure, psig 1,206 3 Minimum Cold Leg Accumulator Water Volume, ft 925 3 Minimum Upper Head Accumulator Water Volume, ft 1,850 System Valves, Interlocks, and Piping Required for the Above All Components which are Operable O 12/93 l

.l Table 6.3.2-3A (Page 1 of 2) l I Sequence of Operations: Injection to Cold Leg Recirculation The following steps would be taken when terminating the injection made and starting the cold leg recirculation moue: (RWST Lo Level Alarm) 1. Verify adequate containment sump level to sustain cold leg recirculation. 2. Verify component cooling water flow to the RHR heat exchangers. 3. Reset Safety Injection. 4. Reset the diesel generator load sequencers. 5. Verify that the containment sump valves to the residual heat removal pumps NI1848 and (NI185A) are open. NOTE: As these valves move off their seats, limit switches will close ND4B and ND19A. 6. Realign power to the common valve between the RWST and the residual heat removal pumps (FW27A). 7. Close the common valve from the RWST to both RHR pumps (FW27A). 8. Close safety injection pump miniflow isolation valves NI1158 and NI1448. { } 9. Realign power to valve NI147A. 10. Close safety injection pump miniflow isolation valve NI147A. 11. Close valves ND30A and ND158 in the crossover line between the two low head headers at discharge side of RHR heat exchanger. 12. Open the two parallel valves in the crossover line between the suction of the safety injection pumps and the suction of the centrifugal charging pumps (NI332A and NI3338). Also verfly that the series valve in the crossover line (NI334) is open or, if necessary, open it. 13. Open the valve in the line from the RHR pumps discharge to the safety injection pump and centrifugal charging pump suction (NI136B and ND58A). NOTE: The valve in the line from the B RHR pump discharge to the safety injection pump suction (NI1368) is interlocked such that it cannot be opened unless either the two parallel safety injection pump miniflow isolation valves (NI144B or NI1158) are shut or the common safety injection pump miniflow isolation valve (NI147A) is shut and the containment sump valve to the B RHR pump (NI184B) is open and either of the isolation valves between the RCS and the RHR pumps suction (ND2A or ND18) is shut. O 1984 L'pdate}}