ML20199G728

Proposed Tech Specs SR 4.7.3b Deleting During SD Requirement & Reflect Appropriate Plant Conditions in Associated 3/4.7.3 Bases

ML20199G728
Person / Time
Site:	Wolf Creek
Issue date:	01/15/1999
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20199G725	List: ML20199G721 ML20199G728
References
NUDOCS 9901220390
Download: ML20199G728 (4)

Text

^ ~ ~ ~

.. Attachment I to WO 99-0002 page 2 of 4  !

l PLANT SYSTEMS 3/4.7.3 COMPONENT COOLING WATER SYSTEM l l

LIMITING CONDITION FOR OPERATION 3.7.3 At least two independent component cooling water loops shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4. ,

i

^ ACTION: 1 With only one component cooling water loop OPERABLE, restore at least two loops to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.3 At least two component cooling water loops shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each va'1ve (manual, power-operated, or automatic) servicing safety-related equipment that is not locked, sealed, or otherwise secured in position is in its correct position. In addition, an ANALOG CHANNEL OPERATIONAL TEST of the surge tank level and flow instrumentation which provide automatic isolation of the non nuclear safety-related portion of the system shall be performed at least once per 31 days;

b. At least once per 18 months @g(M, by verifying that:

1) Each automatic valve servicing safety related equipment or )

isolating the non-nuclear safety-related portion of the system actuates to its correct position on a Safety Injection and on a simulated High Flow and Low Surge Tank Level test signal, and

2) Each OPERABLE Component Cooling Water System pump starts auto-matica11y on a Safety Injection and Loss-of-Power test signal.

c. At least once per 18 months during shutdown, by performing a CHANNEL CALIBRATION of the surge tank level and flow instrumentation which  ;

provide automatic isolation of the non-nuclear safety-related portion of the system.

l n

9901220390 990115 PDR ADOCK 050004 2 P

3 WOLF CREEK - UNIT 1 3/4 7-11

• Attachment I to WO 99-0002

, Page 3 of 4 j PLANT SYSTEMS iiASES 3/4.7.3 C(Mp0NENT COOLING WATER SYSTEM ,

The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses. Each independent CCW loop containi two 100% capacity pumps and, therefore the failure of one pump does not affect the OPERA 8ILITY of that loop. ones.r l  :

l 3/4.7.4 ESSENTIAL SERVICE WATER SYSTEM The OPERA 81LITY of the Essential Service Water System ensures that l sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analysis.

l

! 3/4.7.5 ULTIMATE HEAT SINK

! The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available either to: (1) provide normal i

cooldown of the facility or (2) mitigate the effects of accident conditions within acceptable limits.

The limitations on minimum water level and maximum temperature are based on providing a 30-day cooling water supply from the Essential Service Water pumps to safety-related equipment without exceeding its design basis temperature and is consistent with the recommendations of Regulatory Guide i 1.27, " Ultimate Heat Sink for Nuclear Plants," March 1974.

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERA 8ILITY of the Control Room Emergency, Ventilation System ensures that: (1) the ambient air temperature does not exceed the allowable temperature for continuous-duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will remain habitable for operations personnel during and following all credible accident conditions.

Operation of the system with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the charcoal adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rems or less whole body, or its equivalent.

This limitation is consistent with the requirements of General Design .

Criterion 19 of Appendix A, 10 CFR Part 50. ANSI N510-1975 and N510-1980 will

• be used as procedural guides for surveillance testing. Surveillance testing provides assurance that system and component performances continue to be in accordance with performance specifications for Wolf Creek Unit 1, including i applicable parts of ANSI N509-1976. l l J l

WOLF CREEK - UNIT 1 B 3/4 7-4 Amendment No. Ger&G,89 l n

..=.. . . . . . - - . . - . . . . - . - . - - . . .-. - . - - .. .. ..-,.... - . . . .-... - .. . - - - -

Attachment I to'WO 99-0002 l Page'4.of 4 i

• INSERT A Surveillance Requirement 4.7.3b. verifies proper operation of the CCW valves and pumps on an actuation signal. The CCW System is a normally operating i system that cannot be fully actuated as part of. routine testing during normal }

operation. The 18 month Frequency is based on the need to perform this '

surveillance under the conditions that apply during a unit outage and the i potential for an unplanned transient if the Surveillance were performed with. i the reactor at power, J

-r I

)

i i

-l l 2 i

l

l. I l

l l

1.

I 1'

l' l

1-l l

l i

i i

l l

i l;-

1 i

T t c w , - - - - , - ,.+c - __ . - - - -~ e --,.

Attachment II to WO 99-0002 Page 1 of 1 LIST OF COMMITMENTS l The following table identifies those actions committed to by Wolf Creek ,

Nuclear Opcrating Corporation (WCNOC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be commitments. Please direct questions regarding these commitments to Mr.

Michael J. Angus, Manager Licensing and Corrective Action at Wolf Creek Generating Station, (316) 364-4077.

Cote 4ITMENT Due Date/ Event The amendment will be implemented within 30 days of Within 30 days NRC approval. of Approval of Requested Amendment

!