B13127, Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37

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Proposed Tech Specs,Revising Info on Core Exit Thermocouples,Main Stack wide-range Noble Gas Monitor, Reactor Vessel Water Level & RCS Subcooling Margin Monitor, Per Generic Ltr 83-37
ML20235V093
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 03/01/1989
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20235V087 List:
References
RTR-NUREG-0737, RTR-NUREG-737 B13127, GL-83-37, NUDOCS 8903100035
Download: ML20235V093 (10)
v • d • e


Text

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Docket No. 50-213 l B13127 i

Attachment 1-Haddam Neck Plant.

Proposed Changes to Technical Specification Generic Letter 83 (NUREG-0737) l March 1989 8903100035 890301 PDR ADOCK 05000213 P PDC 1

1 INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.23 The accident monitoring instrumentation channels shown in Table 3.23-1 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.23-1 ACTION: As shown in Table 3.23-1 SURVEILLANCE RE0VIREMENTS Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 3.23-2 I

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TABLE 3.23-1 (Continued)

ACTION STATEMENTS ACTION 1 -

With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels . shown in Table 3.23-1, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 - With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.23-1, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least H0T SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 3 -

With the number of OPERABLE channels less than required by the Minimum Channels OPERABLE requirements, return one channel to operable status within 7 days, or else prepare and submit Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining:

the cause of the malfunction, the plans for restoring the channel to OPERABLE status, and a preplanned alternative method for estimating stack release rates during the interim.

ACTION 4 -

With the number OPERABLE channels less than the Total Number of Channels shown in Table 3.23-1, either restore the inoperable channel (s) to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status and alternate methods in effect for estimating the applicable parameter in the interim.

ACTION 5 -

With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, either restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without shutting down or;

a. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and 3-46a

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b. Restore the system to OPERABLE status at the next- j scheduled refueling.

ACTION 6 -

With the number. of OPERA 3LE accident monitoring instrumentation channels less -than the MINIMUM CHANNELS OPERABLE requirements of Table 3.23-1, restore the inoperable channel (s) to CPERABLE status wf thin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction, the plans for restoring the channel (s) to OPERABLE status, and any alternate methods in affect for estimating the applicable parameter during the interim.

ACTION 7 -

With less than the minimum channel (s) operable, restore the inoperable channel (s) to operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or else establish alternate means to determine if significant fuel failure exists. If still inoperable after 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining: the cause of the inoperability, the plans for restoring operability, and the altr.rnate means established.

ACTION 8 - With the number of channels operable less than the Minimum Channels OPERABLE, determine the subcooling margin once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.- Restore the system to OPLRABLE status at the next scheduled refueling.

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1 INSTRUMENTATION BASES 1.23 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the reconnendations of Regulatory Guide 1.97, Revision 3,

" Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," May 1983 and NUREG-0737,

" Clarification of TMI Action Plan Requirements," November 1980.

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Docket No.' 50-213--

B13127 I

i Attachment,2 Haddam Neck Plant Additional Information Regarding Technical Specification Changes for '

Generic Letter 83-37 March 1989

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U.S. Nuclear Regulatory Commission B13127/ Attachment 2/Page 1 l March 1, 1989 Additional Information Regarding Technical Specification Chanaes for Generic Letter 83-37

1. Are the power-operated relief valves (PORVs) qualified similar to the reactor coolant system (RCS) vent valves so that credit can be given to the PORVs as an alternate path?

Response

.The following information provides the basis for use of the PORVs in lieu of the RCS vent valves to vent noncondensible gases from the Haddam Neck Plant pressurizer.

a, The PORVs have been proven by test to be capable of' opening and closing under full pressure, full temperature conditions. The test results have been submitted to the NRC as required by NUREG-0737, Item II.D.I.

b. The Haddam Neck Plant PORVs are qualified for the harsh environment following a loss of coolant accident. Also, a seismically qualified compressed air supply is also provided to the PORVs.
c. The PORVs are maintained as QA Category I equipment in regards to both valve operations and pressure-retaining capability.
2. Provide the basis for not including the alarm / trip set point and measure-ments range for the containment high-range radiation monitor.

Resoonse Enclosure 3 to Generic Letter (GL) 83-37 provides PWR model Technical Specifications for radiation monitoring instrumentation during plant operation and for postaccident monitoring instrumentation. The model Technical Specification for radiation monitoring during plant operation requires that the alarm / trip set point and measurement range should be specified for the containment high-range radiation monitor. However, at the Haddam Neck Plant, the containment high-range radiation monitor l provides no automatic safety functions and is used only in postaccident l conditions. Therefore it is included in the Technical Specification (the proposed Table 3.23-1) for postaccident monitoring instrumentation and is consistent with the GL 83-37 model Technical Specification for postaccident monitoring instrumentation.

3. Provide the proposed Technical Specification for the containment water level (narrow range).

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U.S. Nuclear. Regulatory Commission B13127/ Attachment 2/Page 2 March 1, 1989

Response

Technical Specification Tables 3.23-1 and 3.23-2 will be revised to include narrow-range containment water level instrumentation and the revised tables will be submitted to the NRC by April 30, 1989.

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