ML20054L158

Proposed Tech Spec Change,Revising Alarm Setpoint for Reactor Core Isolation Cooling

ML20054L158
Person / Time
Site:	LaSalle
Issue date:	07/02/1982
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20054L157	List: ML20054L156 ML20054L158
References
4459N, NUDOCS 8207070205
Download: ML20054L158 (3)

Text

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L ASALLE COUNTY STATION UNIT 1 TECH SPEC CHANGE REQUEST NPF-ll/82-8 Subjec t : Revise RCIC Alarm Setpoint in Surveillance Requirements 4.4.3.2.2.b References (a): FDDR HAI-785, approved July 9, 1980.

(b): GE IDS 234A9310TD Sh 12, Rev. 3.

(c): FSAR Table 7.4-1, Reactor Core Cooling Instrument Specifications, page 7.4-26 (d): Supplement #3, Safety Evaluation Report, NUREG-0519.

(e): License NPF-11, dated April 17, 1982.

Background

References (a) and (b) revised the RCIC alarm setpoint of the high/ low pressure interface valve leakage pressure monitor (lE 51-H021) from 60 psig to 85 psig. The reason for this change was that the RCIC water leg pump discharge pressure is greater than 60 psig and, therefore, without a setpoint change, the suction line high pressure alarm would be energized during normal plant status.

The need for a change in the Technical Specifications was dicussed with Mr. R. Bottimore, who indicated that he would not revise the Technical Specifications until the appropriate FSAR table was revised.

On March 12, 1982, Amendment 60 to the LaSalle FSAR was submitted and contained Reference (c). The receipt o f this amendment is documented in Reference (d), which was issued concurrently with LaSalle license, Re ference (e) .

Discussion Through an oversight, the documented setpoint change was not incorporated in the LaSalle Technical Specifications, which were issued with Re ference (e) . The setpoint specified in 4.4.3.2.2.b.5 should be revised to 90 psig, which allows 5 psig for instrument drif t and reset span, yet still provides control room annunciation prior to suction piping relief valve setpoint o f 100 psig.

Conclusion Commonwealth Edison finds no unreviewed safety question. Because this surveillance demonstrates the operability of the RCIC high/ low pressure interface valve leakage pressure monitor, and since the current setpoint results in an alarm during normal operation, this change is required prior to nuclear pressurization of the reactor vessel in which this monitor is required operable.

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8207070205 820702 4459N PDR ADDCK 05000373 P PDR

Y REACTOR COOLANT SYSTEM

,s SURVEILLANCE REQUIREMENTS (Continued) \

i 4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE:

a. Pursuant to Specification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERABLE by verifying leakage to be within its limit:

1. At least once per 18 months, and

2. Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

In addition, until the LPCS system and the LPCI system injection valve differential pressure-low permissive is modified during or before the first refueling outage, the LPCS system check valve 1E21-F006 and the LPCI system check valves 1E12-F041 A, B, and C shall also be demonstrated OPERABLE by verifying leakage to be within its limit:

1. Whenever the unit has been in COLD SHUTDOWN or REFUELING, after the last valve disturbance prior to reactor coolant system (,

temperature exceeding 200 F

2. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve disturbance except when in COLD SHUTDOWN or REFUELING.

The provisions of Specification 4.0.4 are not applicable for entry into OPERATIONAL CONDITION 3.

b. By demonstrating OPERABILITY of the high/ low pressure interface valve leakage pressure monitors by performance of a:

1. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

2. CHANNEL CALIBRATION at least once per 18 months, f

With the alarm setpoint for the:

1. HPCS system $ 100 psig.

2. LPCS system 5 500 psig.

i 3. LPCI/ shutdown cooling system 5 400 psig.

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r 4. RHR shutdown cooling 5 190 psig.

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5. RCIC5p[psig. )

90 LA SALLE - UNIT 1 3/4 4-8 1

,T Status of Tech Spec Change Requests NRC

1. Topic Submitted Actio n NPF-ll/82-1 Hydrogen Recombiner 5/24/82 Issued Am. 1 Temperature Controller 6/18/82 Setpoint Deviation.

(Required Prior to Criticality).

NPF -11/ 82-2 MSIV Closure Scram Setpoint 5/24/82 Issued Am. 1 (Required Prior 6/18/82 to Criticality).

NPF-ll/82-3 Special Test Exception Change 6/01/82 6/03/82 verbal for Confirmatory Flow Induced Authorization Vibration Test (Required Prior 6/07/82 letter to Test which commenced 6/03/82) . Issued Am . 1.

6/18/82 NPF-ll/82-4 Revised Snubber List 6/07/82 Issue d Am . 1 (License Co ndition 2.C. (5) . (a) 6/18/82 Required Prior to Criticality.

NPF-ll/82-5 Tendon Tables 6/14/82 Issued Am. 1 (License Condition 2.C. (7) 6/18/82 Required Prior to Full Power) .

NPF-ll/82-6 Fire Detector Tables 6/14/82 Issued Am . 1 (License Condition 2.C. (25)(b) 6/18/82 Required Prior to Criticality)

NPF-11/82-7 SRM Countrate 6/14/82 (Required prior to source decay below 3 cps) .

NPF-ll/82-8 Revise RCIC suction delta p 7/02/82 alarm setpoint (Required prior to pressurization).

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