ML20134G340

Proposed Tech Specs 4.3.1.A.4.b Re Surveillance Requirement

ML20134G340
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	11/07/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20134G322	List: ML20134G320 ML20134G340
References
NUDOCS 9611130146
Download: ML20134G340 (8)

Text

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ATTACHMENTH '

ZION NUCLEAR GENERATING STATION i

l MARKED UP ANNOT ATED COPY AND CLEAN COPY OF TECHNICAL <

SPECIFICATIONS I FACILITY OPERATING LICENSES l DPR-39 AND DPR-48 l APPENDIX A TECHNICAL SPECIFICATIONS STEAM GENERATOR WATER LEVEL REQUIREMENTS i

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9611130146 961107 i PDR ADOCK 05006295 P PM

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- SURVEILLANCE REQUIRENENT

' LIM 111NG CONDITION FOR OPERATION -.

The required rr ictor coolant pump (s),

4.3.1.A. 4. a.

l . :1.1. A. 4. At least two of the six heat removal loops if not OPERATING, shall be determined (four~ reactor coolant loops

• and two to be OPERABLE once per week by .

• residual heat removal loops) shall he verifying correct breaker alignments OPERABLE. At least one of these loops and indicated power availabilfty.

, shall be OPERATING.#

l ' b. The required ste'am generator (s) shall be determined OPERABLE by verifying APPL.lCAlllLITY: Mode 4 secondary side-w4de-range water level to be greater than equal to 175 at AtllDN: least once per shift.

a. With less than the above 4hurhd8/

required loops OPERABLE, immediately initiate corrective c. At'least one heat removal loop shall b action to return two loops to a verified to be in operation and OPERABLE status as soon as circulating reactor coolant at least possible; be in COLD SHUTDOWN. once per shift.

w1)hin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With no heat removal loop in operattoo I' - - 'd.

b. With no heat removal loop in the core exit temperature shall be operation: monitored utilizing data from 2 or mor

1) Suspend all operations coro exit thermocouples. The frequent involving a reduction in of temperature readings shall be boron concentration of the adequate to la. ore that the temperatur Reactor Coolant System and; will not incra se above the 10*F subcooling lists between temperature fs

2) Immediately initiate readings.

corrective action to return ' '

the required heat removal loop to operation. .

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• See section 3.3.2.6 for low temperature overpressure protection considerations before star hour provided:

coolant pump. t tion, l

1. All reactor coolant pumps and residual heat removal loops may be and 2) core outlet temperature is maintained at least 10'F below saturation temperature.

l Amendment Nos. 102 & 92

' 73b 1 N' Hl/l 1280

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT , 3.3.1.A. 4. At least two of the six heat removal loops 4.3.1.A. 4. a. The required reactor coolant pump (s).

(four reactor coolant loops

• and two if not OPERATING shall be determined residual heat removal loops) shall be to be OPERABLE once per week by OPERABLE. At least one of these loops verifying correct breaker alignments shall be OPERATING.# and indicated power availability.

APPLICABILITY: Mode 4 b. The required steam generator (s) shall be determined OPERABLE by verifying i

" TION: secondary side narrow range water ievel

a. With less than the above to be greater than or equal to 17% at ,

required loops OPERABLE, least once per shift.

immediately initiate corrective action to return two loops to c. At least one heat removal loop shall be OPERABLE status as soon as verified to be in operation and possible; be in COLD SHUTDOWN circulating reactor coolant at least within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. once per shift.

b. With no hdt removal loop in d. With no heat removal loopsha in Wberation operationi the core exit. temperature

1) Suspend all operations- monitored utilizing data from 2 or more involving a reduction in core exit-thermocouples. The frequency boron concentration of the of temperature readings shall be Reactor Coolant System and; adequate to insure that the tem mrature will not increase above the 10*

. 2) Immediately initiate subcooling limit between temperature

corrective action to return readings.

the required heat removal loop to operation. -

• See section 3.3.2.G for low temperature overpressure protection considerations before starting a reactor-coolant pump. _

1. All reactor coolant pumps'and residual heat removal. loops may be de-energized for up to one hour provided:

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1) no operations are permitted that would cause dilution of the reactor coolant system boron concentration, and 2) core outlet temperature is maintained at least 10*F below saturation temperature.

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73b h endeent Mos. 102 and 92-

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ATTACHMENT C l ZION NUCLEAR GENERATING STATION  !

1 EVALUATION OF SIGNIFICANT IIAZARD CONSIDERATIONS FOR PROPOSED CIIANGES TO l FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECHNICAL SPECIFICATIONS STEAM GENERATOR WATER LEVEL REQUIREMENTS I l

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Commonwealth Edison has evaluated this proposed license amendment and determined that it involves no significant hazard considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no significant hazard considerations if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated;

2. Create the possibility of a new or different kind of accident from any previously analyzed; or,

3. Involve a significant reduction in the margin of safety.

This determination has been performed as indicated below:

1. The proposed changes do not involve a significant increase in the probability or consequences of occurrence of any accident previously evaluated.

Maintaining secondary side steam generator water level greater than or equal to 17% by wide range level indication is the current requirement by the tecimical specifications. By revising the requirement to require using the narrow range water level, no change in l operating practices or plant configuration is made. The minimum requirement of 17% by narrow range level indication is more restrictive and conservative than 17% by wide range indication. The requirement to maintain secondary side steam generator water level greater

than or equal to 17% by narrow range indication is currently required by operations  ;

procedure PT-0, Appendix F-1 and will be maintained. This change ensures that the requirements for natural circulation cooldown are maintained in Mode 4. Therefore, changing this surveillance requirement does not involve a significant increase in the l probability or consequences of an accident previously evaluated.

l 2. The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes do not require a physical alteration of the plant (no new or different equipment will be installed). The Technical Specifications will continue to require OPERABLE steam generator (s) for heat removal functions. The Technical Specifications will continue to require the performance of SR 4.3.1.A.4.b. Changing the SR to use narrow I

level indication correctly states the steam generator water level required to support heat removal function. Thus, this change does not create the possibility of a new or different i kind of accident from any accident previously evaluated.

3. The proposed changes do not involve a significant reduction in a margin of safety.

The proposed changes do not result in a significant reduction in a margin of safety because it has no impact on any safety analysis assumptions. The requirement to have OPERABLE steam generator (s) in MODE 4 for heat removal function is maintained. The requirement to perform SR 43.1.A.4.b is not changed. Changing the SR to use narrow level indication correctly states the steam generator water level required to support heat removal function.

Therefore, this change does not involve a significant reduction in a margin of safety.

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f ATTACHMENT D ZION NUCLEAR GENERATING STATION ENVIRONMENTAL ASSESSMENT STATEMENT FOR PROPOSED CHANGES TO FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECHNICAL SPECIFICATIONS STEAM GENERATOR WATER LEVEL REQUIREMENTS l

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The proposed changes of this license amendment request have been evahiated against the criteria for and identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. It has been determined that the proposed changes meet the criteria l for categorical exclusion as provided for under 10 CFR 51.22(c)(9). The following is a discussion i

I of how the proposed changes meet the criteria for categorical exclusion.

l 10 CFR 51.22(c)(9): Although the proposed change involves a change to a requirement with respect to the installation or use of facility components or to an inspection or Surveillance Requirements:

(i) The proposed change involves no significant hazards considerations (refer to Attaclunent C of this license amendment request);

(ii) There is no significant change in the types or a significant increase in the amounts of any effluent that may be released offsite, since the proposed changes do not affect ,

the generation of any radioactive effluent nor do they afTect any of the permitted release paths; and (iii) There is no significant increase in individual or cumulative occupational radiation exposure. The actions proposed in this request for an amendment do not significantly affect plant radiation levels, and therefore do not significantly affect dose rates and occupational exposure.

Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Based on the aforementioned and pursuant to 10 CFR 51.22(b), no environmental assessment or environmental impact statement need be prepared in connection with issuance of a license amendment incorporating the proposed change.

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