ML20128H301

Proposed Tech Specs,Clarifying & Adding Mode of Applicability for Rod Position Indicator Channels to TS

ML20128H301
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	10/04/1996
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20128H282	List: ML20128H278 ML20128H301
References
NUDOCS 9610090302
Download: ML20128H301 (8)

Text

- _- - . - . - _. - - -_ .- .- . _. _ . ..

1 4

l ATTACHMENT B ZION NUCLEAR GENERATING STATION i

ANNOTATED COPY AND CLEAN COPY OF TECHNICAL SPECIFICATIONS FACILrn' OPERATING LICENSES

} DPR-39 AND DPR-48 APPENDIX A TECHNICAL SPECIFICATIONS ROD POSITION INDICATOR CHANNEL APPLICABILITY 9610090302 961004 PDR ADOCK 05000295 P PDR

i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.3.D Ao61icablQt;y, 'jHodes]Msisdf2 .

4.2.3.D.1.a shall be checked indirectly by-

• Racna$rr- , f.Ztil'oni}j%th_e dondibl6nif'OG$ebE16Fi excore detectors and/or 3;2;,32'd. cannotgWee ' the frelistort'ahallibai thermocouples and/or moveable incore brought:Wigathisaststhe. Rpti)fShutdown!)6ndiMbij detectors over shift; or af ter arry pithirti(outihpNed rod motion of the non-indicating rod, exceeding 12 steps, whichever *

4. DNB Parameters occurs first. I A. The following DNB related parameters b. During operation below 50% of rated shall be maintained within the power, no special monitoring is limits shown during operation. required.

1. Reactor Coolant System Tavg 4.A.1. Each of the parameters listed in FOUR LOOP: s 567.7*F I Specification 3.2.4. A shall be verified - '

2. Pressurizer Pressure ,

to be within its limit at least once per j FO'JR LOOP: 2 2210 psia 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. '

(2195 psig)*

3. Reactor Coolant System Total 2. The Reactor Coolant System total flow I

. Flow Rate rate shall be determined to be within -

FOUR LOOP: 2 362,300 GPM# its limit by measurement at least once  ;

per 18 months. '

B. With any of the above parametera exceeding its limit, restore the parameter to within its limit within P

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to less than 5% of rated thermal power  :

within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l

l I

i i

.- [

Limit not applicable during either a thermal power ramp increase in excess of 5% rated thermal power per j minute or a thermal power step increase in excess of 10% rated thermal power. .

1. Includes a 3.5% flow measurement uncertainty.  !

f i

e 4

55 .

i LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT .-

AteGead;4v: N'bdes ( avd 2_ . j 3.2.3.D.1 -t- If the conditions of Section i

R. ae r e d A c+i m m.- 4.2.3.0.1.a shall be checked indirectly by.

l 3.2.3.D.1 cannot be met the -

i reactor shall be brought to at excore detectors and/or least the Hot Shutdown condition thermocouples and/or moveable incore within four hours and the detectors every shift: or after any reactor trip breakers shall rod motion of the non-indicating remain open. rod, exceeding 12 steps, whichever  !

occurs first.

4. DNB Parameters b. During operation below 50% of rated power, no special monitoring is '

A. The following DNB related parameters shall be maintained within the 4.A.I. Each of the parameters listed in i limits shown during operation.  ;

Specification 3.2.4.A shall be vertfled  !

i 1. Reactor Coolant System Tavg to be within its limit at least once per I 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

FOUR LOOP: s 567.7'F  ;

2. Pressurizer Pressure FOUR LOOP: 1 2210 psia 2. The Reactor Coolant System total flow  !

(2195 psig)* rate shall be determined to be within lts limit by measurement at least once

3. Reactor Coolant System Total l Flow Rate per 18 months. t FOUR LOOP: 2 362,300 GPMi  :

B. With any of the above parameters exceeding its limit. restore the t

' parameter to within its.11mit within i

- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce thermal power to l less than 55 of rated thermal power

~ within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

• l*

f minute or a thermal power step increase in excess of 10% rated thermal power.Listt n .

includes a 3.5% flow measurement uncertainty.

55 Amendment Nos. -156 and W

0 0

D l

l l

ATTACHMENT C ZION NUCLEAR GENERATING STATION EVALUATION OF SIGNIFICANT HAZARD CONSIDERATIONS FOR PROPOSED CHANGES TO FACILITY OPERATING LICENSES DPR-39 AND DPR-48 APPENDIX A TECHNICAL SPECIFICATIONS ROD POSITION INDICATOR CHANNELS OPERABILITY i

e 9

9

Comed has evaluated this proposed license amendment and determined that it involves no 4

signi6 cant hazard considerations. According to 10 CFR 50.92(c), a proposed amendment to an operating license involves no signi6 cant hazard considerations if operation of the facility in accordance with the proposed amendment would not: 1

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 l previously analyzed; or,  ;

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

This determination has been performed as indicated below:

1. 'Ihe pmposed changes do not involve a significant increase in the pmbability or

! consequences of occunence of any accident previously evaluated.

l The proposed requirements for the Rod Position Indicator Channels being applicable in '

MODE I and MODE 2 are acceptable in that these are the only MODES in which power peaking factors are a concern, and the OPERABILITY of Rod Position Indicator Chanttels has the potential to affect the safety of the plant. Control rod alignment limits '

ensure that power distribution and reactivity limits defined by the design power peaking and shutdown margin limits are preserved. In addition, the Rod Position Indicator Channels are not a precursor to any analyzed accident sequence.

l 1 The proposed Required Actions are similar to current Required Actions when the unit is in MODE I and MODE 2. In addition, since there is no safety significance for inoperable Rod Position Indicator Channels for shutdown modes, the proposed Required Actions provide appropriate compensatory actions with the unit in MODE I and MODE

2. Therefore, the initial conditions and system function assum'ed in the UFSAR have not changed. As such, the requirement to have OPERABLE control rod position indication for verification of control rod alignment limitations when the reactor is in MODE I and MODE 2 does not affect any UFSAR accident analysis.

Therefore, this change does not involve a signi6 cant increase in the probability or consequences of an accident previously evaluated.

2. The pmposed changes do not create the possibility of a new or different kind of accident fmm any accident previously evaluated.

The proposed changes do not require a physical alteration of the plant (no new or different equipment will be installed to implement this change). Control rod alignment limits ensure that power distribution and reactivity limits de6ned by the design power

pea' king and shutdown margin limits are preserved. The Technical Specifications will require OPERABLE Rod Position Indicator Channels in MODE I and MODE 2 when control rod alignment and insertion limits are required to maintain acceptable power distribution limits and shutdown margin.

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

The requirement to have OPERABLE Rod Position Indicator Channels when required by associated control rod alignment and insertion limits has been clarified. The LCO will continue to require OPERABLE Rod Position Indicator Channels and an associated Required Action to be in a mode where the Rod Position Indicator Channels are not required. Therefore, this change does not involve a significant reduction in a margin of safety.

p i

i l

l

l l

l i

6 j

i l 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 ROD POSITION INDICATOR CHANNEIS OPERABILITY 9

9

1

=

. . 1

The chinges proposed by this license amendment request have been evaluated against the i i

criteria for and identification of licensing and regulatory actions requiring environmental j assessment in accordance with 10 CFR 51.21. It has been determined that the proposed ,

, changes meet the criteria for categorical exclusion as provided for under 10 CFR 51.22(c)(9).  !

This determination is based on the following discussion.

1 10 CFR 51.22(c)(9): Although the proposed changes involve a change to a requirement with  ;

j respect to the installation or use of facility components or to an inspection or Surveillance Requirements:

(i) The proposed changes involve no significant hazards considerations (refer to j Attachment C of this license amendment request);

l (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 I the generation of any radioactive effluent nor do they affect any of the permitted release paths; and (iii) There is no significant increase in individual or cumulative occupational radiation l

exposure. The actions proposed in this request for an amendment do not significantly affect plant radiation levels, and therefore do not significantly affect I dose rates and occupational exposure.

Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR St.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.

9