ML20237F121

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Forwards Revised Pages 28 & 41 to Reg Guide 1.97,Rev 5, Position.Rev Incorporates Potential Flow Path to Environ from Auxiliary Feedwater Turbine Exhaust
ML20237F121
Person / Time
Site: Rancho Seco
Issue date: 12/23/1987
From: Coward G
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To: Miraglia F
Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.097, RTR-REGGD-1.097 AGM-TA-87-283, NUDOCS 8712290373
Download: ML20237F121 (4)


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I"') SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O P. O. Box 15830, Sacramento CA 95852-1830,(916) 452-3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA DEC 2 31987 AGM/TA 87-283 U. S. Nuclear Regulatory Commission Attn: Frank J. Miraglia, Jr.

Associate Director for Projects Philips Bldg.

7920 Norfolk Avenue Bethesda, MD 20014 DOCKET 50-312 RANCHO-SEC0 NUCLEAR GENERATING STATION LICENSE NO. DPR-54 SMUD POSITION TO REGULATORY GUIDE 1.97, REVISION 5

Dear Mr. Miraglia:

Please find attached revised pages 28 and 41 to the District's Regulatory Guide 1.97 position. These pages comprise Revision 5 to the 1.97 position that was submitted to the Staff on September 14, 1984. Variable 75, " Vent from Steam Generator Safety Relief Valves," has been changed to include steam release from the auxiliary feedwater (AFW) turbine exhaust. Under certain accident scenarios, a potential for radioactive airborne release via the turbine exhaust exists. The present design vents the auxiliary feedwater pump turbine exhaust to the atmosphere.

This revision incorporates the potential flow path to the environment from the AFW turbine exhaust.

Please contact me if you have any questions. Members of your Staff with questions requiring additional information or clarification may contact John Atwell at (209) 333-2935, extension 4917.

Sincerely, 4 4 i eorge A. Coward  ;

Assistant General Manager, i Technical and Administrative Services )

8712290373 871223 ~

PDR ADOCH 05000312 Attachment P PDR l cc: G. Kalman, NRC, Bethesda A. D'Angelo, NRC, Rancho Seco

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J. B. Martin, NRC, Walnut Creek i\

RANCHO SECO NUCLEAR GENERATING STATION O 1444o Twin Cities Road, Herald, CA 95638 9799;(209) 333-2935 L

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SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO GENERATING STATION UNIT NO. 1 REGULATORY GUIDE 1.97 POSITION  ;

REVISION 5 (CORRECTED PAGES ONLY)

DECEMER 1987 i

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,s Va riable ' Explanation

'72 . . These Radiation Monitors were installed to meet the requirements of NUREG 0737, Cluffication II.F.1, Attachment 1, and as such, the Reg. Guide 1.97 Category classification is not applicable (accepted by the NRC in the letter dated 5/1/80, Reid to Mattimoe)-

73 The condenser air jet ejector discharge is vented through the Auxiliary Building comon stack (variable 72). Therefore, this variable is not applicable as a post accident monitored variable. .In addition, the condenser air removal system is monitored by a . Category 3 Type E system (see variable 29).

74 The Comon Plant Vent is the Auxiliary Building vent (variable

72) and, therefore, this variable is not applicable. The containment purge discharges through dedicated vents. However, a the Reactor Bui: ding purge fans are tripped off on a high radiation' signal of approxinjately 10-o micro Ci/cc for the p(variable 32,. Containment Effluent Radiation). articulated monitor or 75 Externally mounted radiation monitors were installed to provide combined noble gas effluent monitoring for the Steam Generator. .

Safety Relief Valves and Atmospheric Dump Valves (ADV) meeting; the requirement of NUREG 0737., Clarification Item II.F.1, Attachment 1 and, as such, the Reg. Guide 1.97' category classification is not' applicable (accepted by the NRC in the letter dated 5/1/80, Reid to Mattimoe).

These radiation monitors, along with the Steam Generator Safety Valve and ADV position indications (acoustic leak detection system), and the plant computer which monitors the number and -

durathn of valves actuated, provide the necessary input for 1 calculation of release rates per unit time as required by NUREG l 0737, Clarification II.F.1, Attachment 1.. (This is consistent I with the B&WOG Reg. Guide 1.97 task force's generic position.)

In similar fashion, these radiation monitors plus position of the turbine-inlet valve (FY-30801) and the main steam to aux feed turbine valves (HV-20569 and HV-20596) provide the necessary inputs to calculate the release rate per unit time for d

the Auxiliary Feedwater Pump Turbine exhaust (K-308).

Other variables which may be used to refine the calculation are Steam Generator Pressure (Category 1, variables 2, 12, 16, 24, and 29).

76 Effluents are discharged through other monitored plant vents (see variables 32, 33, 72, 75, and 77) . Therefore, this variable is nbt applicable.

l MEM0581(D2.12) Rev 5 41 L _ _____--__. _____________ _ o