ML20199A610

Proposed Tech Specs Pages,Updating TS Bases Section 3/4.4.9, to Reflect Results of Revised Analysis That Was Reviewed & Accepted by NRC as Part of License Amends 55 & 44.Analysis Results Not Incorporated Into TS Bases Due to Oversight

ML20199A610
Person / Time
Site:	South Texas
Issue date:	11/05/1997
From:	HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20199A194	List: ML20199A610 ST-HL-AE-5746, Requests Update to TS Bases Section 3/4.4.9, Pressure/ Temperature Limits, to Reflect Results of Revised Analysis That Was Reviewed & Accepted by NRC as Part of License Amends 55 & 44
References
NUDOCS 9711180033
Download: ML20199A610 (2)

Text

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l PFACTOR COOLANT SYSTEM BASES LOW TEMPERATURE OVERPRESSURE PROTECTION (Continued) overshoot beyond the PORV Setpoint which can occur as a result of time delays instrument uncertainties, and single ,

in signalToprocessing failure. ensure thatand massvalve andopening, heat input transients more severe than those i assumed cannot occur Technical Specifications require lockout of all high .

I head safety injection aumas while in H00E 5 and MODE 6 with the reactor vessel head on. All but one 11g'1 head safety injection pump are required to be locked out in H0DE 4. Technical Specifications also require lockout of the positive dis 31acement pump and all but one charging pump while in H0 DES 4, 5, and 6 with tie reactor vessel head installed and disallow start of an RCP if secondary temperature is more than 50'F above primary temperature.

Administrative controls and two RHR relief valves will be used to provide cold overpressure protection (COMS) during the ASME stroke testing *of two administrative 1y declared inoperable PORVs. During the performance of the PORY function test, two RHR trains will be OPEPABLE and in operation with the auto closure interlock bypassed (or deleted) to provide COMS, With one PORV inoperable, COMS will be provided during the ASME test by the OPERABLE PORV and one RHR relief valve associated with an OPERABLE and operating RHR train which has the auto closure interlock bypassed (or deleted). Each RHR reitef valve provides sufficient capacity to relieve the flow rendting from the maximum ciarging flow with concuttent_ loss of letdown.

7he RRR pump design developed head, correspondEg to the design floWiitiof 3400 gpm, is 205 ft and the actual pun.p developed pressure is 115 psig. This b results in actuation of the RHR relief valves at a RCS pressure of _

(approximately 485 psig (600 psig - 115 psig). 7 ,

Therefore two OPERABLE and operating RHR trains at one OPERABLE PORV and one OPEPADLE and operating RHR train will provide adequate and redundant overpressure protection. Use of the RHR relief valves will maintain the R S

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paisturJLhelow the low temperatuteJhdpoint a of7he TeclinEl'~SpecifiEation -

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Qimit curve (550 psig, Ref. Tecfinical Specification Fig. 3.4-2).f ~

With regard to the MODE 6 applicability of this Technical Specification, the statement "with the head on the reactor vessel" means any time the head is installed with or without tensioning the RPV studs.

The Maximum Allowed PORV Setpoint for the COMS will be updated based on the results of examinations of reactor vessel matetici irradiation surveillance specimens performed as required by 10 CFR Part 50, Appendix H.

3/4.a.10 STRUCTURAL INTEGRITY The inservice inspection and testing programs for ASME Code Class 1, 2, and 3 components ensure that the structural integrity and operational readiness of these components will be maintained at an acceptable level SOUTH TEXAS - UNITS 1 & 2 B 3/4 4-15 Unit 1 - Amendment No. 4,s+, 55 Unit 2 - Amendment No. N,44 DO 99 P PDR

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Insert A. for page B 3/4 4-15: .

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" Analysis conservatively demonstrates that the RiiR relief valves limit RCS pressure to approximately 590 psig."

!asert B for page B 3/4.415:

... limits or ASME Section III, Appendix 0."

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