ML20044F987

Proposed TS 3/4.4.2 Re LCO for SRVs & 4.4.2.1 Re Demonstration of Operability of Acoustic Monitor for SRVs

ML20044F987
Person / Time
Site:	Hope Creek
Issue date:	05/21/1993
From:	Public Service Enterprise Group
To:
Shared Package
ML20044F985	List: ML20044F984 ML20044F987
References
NUDOCS 9306010287
Download: ML20044F987 (6)

Text

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f ATTACHMENT 2 LICENSE AMENDMENT APPLICATION SAFETY / RELIEF VALVE TESTING REQUIREMENTS FACILITY OPERATING-LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 i

TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specifications for Facility Operating License No. NPF-57 are affected by this license amendment request:

Technical Specification Pace 3.4.2.1 3/4 4-7 4.4.2.2 3/4 4-8 Bases 3/4.4.2 B 3/4 4-2 V

b 9306010287 930521 PDR ADDCK 05000354 p

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I REACTOR ~00LANT SYSTEM 3/4. 4. 2 SAFE 7Y/REL:EF '!ALVE5

• AFETV/DELIEF VALVE 5 L!MITING CONDIT!ON r0R OPERATION t

3. A. 2.1 The safety valve function of at least 13 of t

coiantsystemsafety/reliefvalvesshallceOPERABLE"gefollowingreactor

.a tn the spec fiec :o: e safety valve function lift settings:""

4 safety-relief valves @ 1108 psig +1%

5 safety-relief valves @ 1120 psig 71%

5 safety-relief valves @ 1130 psig _;1%

APDLICABILITY:

GPERAT:0NAL CONDITIONS 1, 2 anc 3..

ACT!0N:

With the safety valve function of two or more of the above listed fourteen a.

safety / relief valves inoperaDie, be in at least HOT SHUTDOWN within 12 noun and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With one or more safety / relief valves stuck open, provided that suporession pool average water temperature is less than 110*F, close the stuck open safety relief valve (s); if unaDie to close the stuck open valve (s) within 2 minutes or if suppression pool average water temperature is 110*F or greater, place the reactor mode switch in the Shutdown position.

With one or more of the above required safety / relief valve acoustic mon 1-c.

tors inoperable, restore the inoperable monitors to OPERABLE status witnin

+

7 days or te in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLO SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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i "5RVs which perform as ADS function must also satisfy the OPERABILITY requirements of Specification 3.5.1, ECCS-Operating.

• • The lift setting pressure shall correspond to ambient conditions of the valses at nominal operating temperatures and pressures.

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1. 5RVs which perform a low-low set function must also satisfy the OPERABILIT'r requirements of SpecificationlJ.1.A A Safety / Relief Valves Low-Low Set Function.

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HOPE CREEK 3/4 4-7

t REACTOR COOLANT SYSTEM IURVEILLANCE REOUIREMENTS 4.4.2.1 The acoustic monitor for each safety / relief valve shall be demonstratec OPERABLE.ith the setpoint verified to be 1 30% of full open noise level"*

oy performance of a:

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CHANNEL FUNCTIONAL TEST at least once per 31 days, and a-asse m\\Au s l

3.

CHANNEL CALIBRATION at least once per 18 months".

4.4.2.2 Atleast1/2ofthesafetyreliefvalved'nallberemoved,setpressure tested and reinstalled or replacec with spares that have been previously set oressure testec and stored in accordance with manufacturer's recommendations at least once per 13 months, and they shall be rotated such that all 14 safety reliefvalvedlareremoved,setpressuretestedandreinstalledorreolacedwitn rascar scares tnat nave oeen previously set pressure tested and stored in accordance with manufacturer's recommendations at least 'once per 40 months.

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"The provisions of Specification 4.0.4 are not applicable provided the Surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.

• • Initial setting shall be in accordance with the manufacturer's recommendations.

Adjustment to the valve full open noise level shall be accomplished after the initial noise traces have been analyzed.

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h HOPE CREEK 3/4 4-8 Amendment No. 35 1

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t INSERT FOR PAGE 3/4 4-8; 4.4.2.3 The safety relief valve main (mechanical) stage assemblies shall be set pressure tested, reinstalled or replaced with spares that have been previously set pressure tested and stored in accordance with manufacturer's recommendations at least once every 5' years.

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REACTOR COOLANT SYSTEM

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BASES Neutron flux noise limits are also established to ensure early detection of limit cycle neutron flux oscillations.

BWR cores typically operate with neutron flux noise caused by random boiling and flow noise.

Typical neutron flux noise levels of 1-12% of rated power (peak-to peak) have been reported for the range of low to high recirculation loop flow during both single and dual recirculation loop operation.

Neutron flux noise levels which significantly bound these values are considered in the thermal / mechanical design of GE BWR fuel and are found to be of negligible consequence.

In addition, stability tests at operating BWRs have demonstrated that when stability related neutron flux limit cycle oscillations occur they result in peak-to peak neutron flux limit cycles of 5-10 times the typical values.

Therefore, actions taken to reduce 1

neutron flux noise levels exceeding three (3) times the typical value are suf-ficient to ensure early detection of limit cycle neutron flux oscillations.

Typically, neutron flux noise levels show a gradual increase in absolute magnitude as core flow is increased (constant control rod pattern) with two reactor recirculation loops in operation.

Therefore, the baseline neutron flux noise level obtained at a specific core flow can be applied over a range of core flows.

To maintain a reasonable variation between the low flow and high flow end of the flow range, the range over which a specific baseline is applied should not exceed 20% of rated core flow with two recirculation loops in operation.

Data from tests and operating plants indicate that a range of 20% of rated core flow will result in approximately a 50% increase in neutron flux noise level during operation with two recirculation loops.

Baseline data should be taken near the maximum rod line at which the majority of operation will occur.

However, base-line date taken at lower rod lines (i.e., lower power) will result in a conser-vative value since the neutron flux noise level is proportional to the power level at a given core flow.

3/4.4.2 SAFETY / RELIEF VALVES The safety valve function of the safety / relief valves operates to prevent the reactor coolant system from being pressurized above the Safety Limit of 1375 psig in accordance with the ASME Code.

A total of 13 OPERABLE safety / relief valves is required to limit reactor pressure to within ASME III allowable values for the worst case transient.

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/ingshutdownemonstragonofthe ety/ relief'valvelift/ettingswi(occuronly

.a sa y/ relief lives will ( removed a either set res-retestefor ith spares hich have en previou y set press re j

tested and stot % in a cordance wy' h manufact r's reco ndations at he specifiptf frequency /

/

/

'i The 1ow-low set system ensures that safety / relief valve discharges are minimized for a second opening of these valves, following any overpressure tran-sient.

This is achieved by automatically lowering the closing setpoint of two valves and lowering the opening setpoint of two valves following the initial opening.

In this way, the frequency and magnitude of the containment blowdown duty cycle is substantJally reduced.

Sufficient redundancy is provided for the low-low set ~ system such that failure of any one valve to open or close at its reduced setpoint does not violate the design basis.

HOPE CREEK B 3/4 4-2

i INSERT FOR BASES PAGE B 3/4 4-2:

Demonstration of the safety relief valve lift settings occurs only during shutdown.

The safety relief valve pilot stage assemblies are set pressure tested in accordance with the recommendations of General Electric SIL No. 196, Supplement 14 (April 23, 1984), " Target Rock 2-Stage SRV Set-Point Drift."

Set pressure tests of the safety relief valve main (mechanical) stage are conducted at least once every 5 years.

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