ML20096D702

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Proposed Tech Spec to Install New Remote Shutdown Sys
ML20096D702
Person / Time
Site: Crystal River 
Issue date: 08/30/1984
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20096D700 List:
References
GL-81-12, NUDOCS 8409060253
Download: ML20096D702 (7)


Text

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FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 REQUEST NO.124, REVISION 0 REMOTE SHUTDOWN CONTROL AND INSTRUMENTATION LICENSE DOCUMENT INVOLVED Technical Specifications PORTION 3.3.3.5 Remote Shutdown System DESCRIPTION OF REQUEST Revise the Remote Shutdown Instrumentation Specification to be consistent with the instrumentation listed in Florida Power's submittal, dated October 29,1982," Generic Letter 81-12 on Fire Protection". Additionally add operability and surveillance requirements for the remote shutdown system transfer switches. This system will be installed during Refuel V, with Technical Specification implementation following startup.

REASON FOR REQUEST This Change Request is being submitted to revise the designated Remote Shutdown Instrumentation. These instruments and the transfer switches are being modified or added to comply with Section III. G, Appendix R,10 CFR 50. The safety evaluation for this system was transmitted to Florida Power on January 6,1983 and requests these specification changes prior to the new Remote Shutdown Panel operation.

EVALUATION OF REQUEST The revisions proposed herein are consistent with Florida Power's submittal concerning Remote Shutdown which has been evaluated and approved by the NRC Staff. The addition of the surveillance and operability requirements for the Remote Shutdown equipment are additional limitations not presently !r.cluded in the Technical Specifications and, as such, will enhance plant safety.

REFERENCES 1.

Generic Letter 81-12," Fire Protection Rule," February 20,1981.

2.

FPC to NRC Correspondence, " Generic Letter 81-12 on Fire Protection", #3F1082-2, October 29,1982.

3.

NRC to FPC Correspondence," Appendix R Safety Evaluation," #3N0183-05, January 6,1983.

4.

FPC to NRC Correspondence, " Appendix R to 10 CFR 50, Fire Protection,"#3F 0283-11, February 11,1983.

5.

Memo to T. Wambach from M. Virgilio concerning "Model Technical Specifications for Alternative Shutdown Systems Required by 10 CFR 50, Appendix R", March 10,1933.

8409060253 840830 PDRADOCK05000g F

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302/ LICENSE NO. DPR-72 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Request:

Florida Power Corporation requests issuance of an amendment to Crystal River Unit 3 Technical Specification to replace current remote shutdown instrumentation requirements with requirements for the new remote shutdown system. This system is being'added as required by the fire protection rule, and should be operational by cycle six (late 1985).

Sigolficant hazards consideration determination:

(x)

Amendment involves no significant hazards consideration.

()

Amendment involves significant hazards consideration.

Basis for Determination:

This amendment is considered not likely to involve significant hazards consideration because it is a change to make the facility and license conform to the regulations of 10CFR50, Appendix R.

Requested Implementation Date:

Florida Power Corporation requests an implementation date prior to achieving Mode 3 for cycle six.


m INSTRUMENTATION REMOTE SHUTDOWN SYSTEM LIMITING CONDITIONS FOR OPERATION 3.3.3.5 The remote shutdown system transfer switches, and monitoring instrumentation channels shown in Table 3.3-9 shall be OPERABLE.

The readouts for the monitoring instrumentation channels shall be displayed on the remote shutdown panel.

APPLICABILITY:

MODES 1,2 and 3.

ACTION:

a.

With the number of OPERABLE remote shutdown monitoring instrumentation channels less than required by Table 3.3-9, restore the inoperable channel (s) to OPERABLE status within 30 days, or be 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 />.

b.

With one or more remote shutdown system transfer switches inoperable, restore the inoperable switch (s) to OPERABLE status within 30 days, or be 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 />.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.5.1 Each remote shutdown monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3-6.

4.3.3.5.2 Each remote shutdown system transfer switch shown in Table 3.3-9 shall be demonstrated OPERABLE at least once per 18 months, by operating each piece of equipment required for safe shutdown (as specified in the fire protection plan) from the remote shutdown system panel.

CRYSTAL RIVER - UNIT 3 3/4 3-34

TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM MINIMUM CHANNELS MONITORING INSTRUMENT OPERABLE I

1.

Reactor Coolant Pressure (Wide Range) 1 2.

Pressurizer Level 1

3.

Reactor Coolant Hot Leg Temperature (Wide Range) 1/ loop 4.

Steam Generator Pressure 1/ steam generator 5.

Steam Generator Level (Startup) 1/ steam generator 1

6.

Steam Generator Level (Operating Range) 1/ steam generator lY 7.

Source Range Flux 1

8.

Emergency Feedwater Flow Rate 1/ steam generator 9.

Emergency feedwater normal supply tank Level I

TRANSFER SWITCHES SWITCH LOCATION 1

l Remote Shutdown Panel Control Power, Train - A 4160 ES-A Switchgear Room 108 Foot Elevation, Control Complex Remote Shutdown Panel Control Power, Train - B 4160 ES-B Switchgear Room 103 Foot Elevation, Control Complex l

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TABLE 4.3f f

l REMOTE SHUTDOWN MONITORING INSTRUMENTATION i

SURVEILLANCE REQUIREMENTS

/

CHANNEL CHANNEL

. INSTRUMENT CHECK CALIBRATION 1.

Reactor Coolent Pressure (Wide Range)

M R

l 2.

Pressurizer Level M

R n !} '

/

3.

Reactor Coolant Hot Leg Temperature M

R (Wide Range) i

, 1 4.

/ Steam Generator Pressure M

R Steam Generator Level (Startup)

M R

6.

Steam Generator Level (Operating Range)

M R

g 7.

Source Range Flux M

R

/

8.

Emergency Feedwater Flow Rate M

R 9.

Emergency feedwater normal supply M

R tank Level

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CRYSTAL RIVER - UNIT 3 3/4 3-36

M lj 3/4.3. INSTRUMENTATION

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BASES W

3/4.3.3 ~ MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the r6diation monitoring channels ensures that

~~17 1)' the radiation levels are continually measured in the. areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

1 3/4.3.3.2 INCORE DETECTORS The OPERABILITY of the incore detectors ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of 'the reactor core.

See Bases Figures 3-1 and 3-2 for' examples of acceptable minimum incore detector arrangements.

3/4.3.3.3 SEISMIC INSTRUMENTATION 14 The OPERABILITY of the seismic instrumentation ensures that suffi-cient capability f s available to promptly determine the magnitude of a seismic event so that'the response of those features important to-safety may be evaluated. This capability is required to permit comparison of h'..

the measured response to that used in the-design basis for the facility.

This instrumentation is consistent with the recommendations.of Safety Guide 12 " Instrumentation for' Earthquakes", March-1971.

L 3/4.3.3;4 METEOROLOGICAL INSTRUMENTATION l -.

- The OPERABILITY of the meteorological instrumentation ' ensures that L

sufficient meteorological data -is available for estimating potential l

radiation doses to the public 'as a result of routine or accidental release of radioactive materials to the atmosphere.

This capability is l ;~_

L required to evaluate the need ~for initiating protective measures to protect.the health and safety of the public.

This instrumentation is consistent with the recommendations of Regulatory Guide 1.23 "Onsite 5?m Meteorological Programs", February 1972.

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CRYSTAL RIVER - UNIT 3 B 3/4 3-2 e

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~ 3/4.3 INSTRUMENTATION s-BASES 3/4.3.3.5 REMOTE SHUTDOWI INSTRUMENTATION The operability of the Remote Shutdown System ensures that a fire in the Main Control ' Room or Cable Spreading Room will not preclude safe shutdown.

The equipment required to remain operable for safe plant shutdown is described in the Crystal River Unit 3 Fire Protection Plan.

The equipment required to be_ operated from the Remote Shutdown Panel to demonstrate transfer switch operability is also described'in the Fire Protection Plan.

3/4.3.3.6 POST-ACCIDENT INSTRUNENTATION The OPERABILITY of the post-accident 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 recommendations -of Regulatory Guide 1.97, " Instrumentation for Light-Water Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1975.

3/4.3.3.7 FIRE DETECTION INSTRUMENTATION The OPERABILITY of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.

This capa-bility is required in order to detect and locate fires in their early stages.

Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.

In the event that a portion of the fire detection instrumentation is inoperable, the - establishment of frequent fire patrols in the affected areas is required' to provide detection capability until the inoperable instrumentation is returned to service.

-CRYSTAL RIVER - UNIT 3 B 3/4 3-3

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