ML20087A509

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Revised Selected Licensee Commitments Manual
ML20087A509
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 11/30/1991
From: Frobe H
DUKE POWER CO.
To:
NRC
References
PROC-911130, NUDOCS 9201090190
Download: ML20087A509 (10)
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Text

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i Jarnary 3, 8992 i

P RC: Catawba Nuclear Station t elected LL:ensee Cornmitments Effectivt 's 1/91 Pleas:; revise your copy of the Selecta! Licensee Commitments manual as follows:

Brmove thesg.y.agn Insert these nages LOEP 1, 2, 3 LOF.P 1, 2, 3 16.2-1 16.2 1 16.2 2 16.2 2 16.2 3 1623 16.5 1 16.5 2 16.5-3 If you have any questions or probicms, I may be contacted at (704) 3"; 7720.

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DUKE POWER COMPANY I CATAWBA NUCLEAR STATION l i

SELECTED LICENSEE COMMITNENTS '

MANUAL LIST OF EFFECTIVE PAGES i

I hetg Pevision Date  ;

LOEP-1 11/91 ,

LOEP-2 11/91

.LOEP 3 11/91 Tab 16.0-  !

16.0-1 12/90  !

Tab 16.1-16.1-1 ,

Tab 16.2-i 16,2-1 11/91 ,

16.2-2 11/91 .

1 16.2-3 11/91 IAb 16.1 16.3-1 11/91 16.3 11/91 l

= Table 16.3-1 11/91  ;

. Tab 16.4

13) 16.5 ,.

16.5-1 11/91  ;

16,5-2 11/91 ,

16.5-3 11/91 .

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Tab 16 1 Tab 16.7 Tab 16.8 Tab 16.9 16.9-0 12/90 16.9-1 12/90 16.9-2 12/90 16.9-3 12/90 16.9-4 12/90 16.9-5 12/90 16.9-6 12/90 16.9-7 12/90 16.9-8 12/90 16.9-9 12/90 16.9-10 12/90 16.9-11 12/90 16.9-12 12/90 16.9-13 10/91 16.9-14 10/91 16.9-14a 10/91 16.9-14b 10/91 16.9-14c 10/91 16.9-14d 10/91 16.9-15 5/91 16.9-16 5/91 16.9-17 .5/91 Table 16.9-3_1 of S 12/90 l

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Table 16.9-3 2 of 5 12/90 i Table 16.9-3 3 of 5 12/90 Table 16.9-3 4 of 5 12/90 Table 16.9-3 5 of 5 12/90 Tab 16.10 16.10-1 2/91 -

16.10-2 2/91 Tab 16.11 Tab 14%12 Tab 16.13

- 16.13-0 12/90 16.13-1 12/90 Tab 16.14 Iab 16.15 Anpanslix Directive 3.1.5 1 of 7 Directive 3.1.5 2 of 7 Directive 3.1.5 3 of 7 Directive 3.? J 4 of 7 ,

' Directive 3.1.5 5 of 7 Directive 3.1.5 6 of 7 Directive 3.1.5 7 of 7 Directive 3.1.5 Attachment i 1 of 1 Directive 3.1.5 Attachment 2 1 of 1 Directive 3.1.5 Attachment 3 1 of 1 Directive 3.1.5 Attachment 4 1 of 1 Directive 3.1.5 Attachment 5 1 of 1 11/91 Page 3

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1 16.2 , APPLICABILITY This section pro; ides the general roquirements applicable to each of the COMMITMENTS and Testing requirements within Section 16.0, Selected Licensee Comniltments (SLCs).

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16.2.1 Compliance with the COMMITMENTS is required as specified. I Whta a COMMITMENT is not met, the associated REMEDIAL ACTION (S) )

shall be mot.

16.2.2 Noncompliance with a COMMITMENT exists when the requirements of both the COMMITMENT and the specified REMEDIAL i ACTION are not met within the specified time. If compliance with-a COMMITMENT is restored prior to expiration of the specified time intarval, completion of the REMEDIAL ACTION (S) is not required.

16.2.3 Entry into an OPERATIONAL MODE or other specified condition shall not be made when the conditions for the COMMITMENT are not met and the associated REMEDIAL ACTION requires a shutdown

- if they are not met within a specified time interval. Entry into an OPERATIONAL MODE or specified condition may be made in accordance with the REMEDIAL ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIOHAL MODES as required to comply with REMEDIAL ACTION requirements. Exceptions to these requirements are st.ated in the individual COMMITMENTS.

16.2.4_ COMMITMENTS including the associated REMEDIAL ACTIONS shall apply to each unit individually unless ott.orwise indicated as follows:

a. Whenever the COMMITMENT refers to systems or components which are shared by both units, the REMEDI AL ACTIONS will apply to both units simultaneously. This will be indicated in the REMEDIAL ACTIONS;
b. Whenever the COMMITMENT applies to only one unit, this will be identified in the APPLICABILITY section of the COMMITMENT; and
c. Whenever_ certain portions of_ a COMMITMENT contain operating parameters, setpoints, etc. , which are dif ferent for each unit, this vill be identified in parentheses or l footnotes. -(for example, " ... flow rate of 54,000 cfm l (Unit 1) or 43,000 cfm (Unit 2)...").

16.2.5 Testing Requirements shall be met during the OPERATION MODES or other conditions specified for an indivitial COMMITMENT unless otherwise stated in an individual Testing .4equirement or Reference.

16.2-1 11/91

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e 16.2.6 Each Testing Requirement shall be performed on its j rpecified frequency with a maximum allowable extansion not to exceed 25% of the test f requency. The phrase "at least" associated with a testing frequency does not negate this tolerance value, and permits the performance of more frequent testing activities. This tolerance is necessary to provide operational flexibility because of scheduling and t>erformance considerations.

16.2.7 Under this criteria, equipment, systems or components are assumed to ve OPERABLE if the associated Testing Requirements have been satisfactorily performed within the specified test frequency.

Nothing in this provision is to be construed as defining equipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Testing Requirements.

Failure to perform a Testing Requirement within the specified frequency shall constitute a failure to meet the OPERABILITY Requirements for a COMMITMENT. Exceptions to these requirements are stated in the individual COMMITMENTS. The time limits of the REMED 'CTION requirements are applicable at the time it is ident! J that a Testing Requirement has not been performed. The REMEDI AL ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the Testing Requirement when the allowable outage time limits the REMEDIAL ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Testing procedures do not have to be performed on inoperable equipment.

16.2.8 During initial plant startup or following extended plant outages, the applicable testing activities must be performed within the stated test frequency prior to placing or returning the system or equipment to OPERABLE status.

Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Testing Requirement (s) associated with the COMMITMENT have been performed within the specified frequency.

16.2.9 Testing Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 compcnents shall be applicable as follows:

a. Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1,2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10CFR 50, Section 50.55a(g)(6)(1);
b. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by tne ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these I

16.2-2 I 11/91

s COMMITMENTS  ;

ASME Boiler and Pressuro Required frequencies Vessel Code and applicable for poriormin9 Addenda terminology for inservice inspection inservico inspection and and testing activition {

geting activities Weekly At least once por 7 Monthly days Quarterly or overy 3 months At least onco por 51 Somlannually or every 6 days months At least once por 92 Every 9 months days Yearly or annually At least once por 184 days At least once por 276 .

days At least once por 366 days t'

c. The provisions of Section 16.2.6 are applicable to the above required frequenclos for performing inservice inspection and testing activities;
d. Performance of the above inservice inspection and testing '

activities shall be in addition to other speciflod Testing Requirements; and

o. The ASME Bollor and Pressure Vessel Code supersedes the .

requirements of any COMMITMENT unless an exception to the Codo has been approved.

16.2.10 Testing Requirements shall apply to each unit individually unless otherwise indicated as stated in Section 16.2.4 for indiv!. dual COMMITMENTS or whenever certain portions of a COMMITMENT contain testing paramotors different for each unit, which will bo identiflod in parenthesos or footnotes.

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16.'2-3 11/91

9 I 16.5 REACTOR COOLANT SYSTEM MID-LOOP OPERATION WITH IRRADIATED FUCL IN THE CORJE 16.5-1 COMMITMENT

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Operations with Reactor Coolant (NC) system level less than or equal to 16% with fuel in the mre shall be conducted under the following conditions:

1) At least one hot leg will be maintained with no S/G nozzle dam installed until the reactor vessel head has been removed.
2) If S/G nozzle dams are to be used, one hot leg dam and a hot or cold leg manway on the associated 9/C shall remain out anytime the reactor vessel head is in . ace. If a cold leg manway is being used, then all cold leg nozzle dams must be installed.
3) Two independent trains of NC level instruments are required.

These instruments shall have independent transmitters and shall not include the NC System jhtglass (NCLG-6450) or tygon tubing.

4) Two core exit thermocouples shall be maintained operating with temporary high alarnr set at 140" F and monitored except as noted below:
  • Final disconnection of the last two core exit thermocouples shall occur no sooner than two hours prior to reactor vessel head removal.
  • Reconnection of at least two thermocouples within two hours after reinstalling the reactor vessel head.
  • The total time without thermocouple indication shall not exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5) Three power sources shall be available as follows:
  • Two off-site power sources and one D/G, or
  • One off-site power source and two D/Gs.
6) Two independent makeup paths of borated water shall be available, during each of the following conditions:

a) Reactor Coolant System intact:

16,5-1 11/91

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  • One Safety Injection Pu',np (NI) having its breaker installed in its associnted cubicle and a flow path available f rom the FWS7' to the NC System.

b) Reactor Coolant System open to Containment atmosphoro via a hot leg vent paths

  • One of the following gravity flowpaths
  • FWST through ND-33 to the cold legs via NI-173A and/or NI-1788.
  • FWST through the ND suction lines to the hotlegs.
  • FWST through ND-33 to the hotlegs via NI-1838.

NOTE: The number of open containment penetrations is limited such that the penetrations can be closed within two hours of losing ND.

7) Containment Closure must be established. Containment Closure is verified by the performance of PT/1/(2)/A/4200/02C-I, Containment Closure Verification, with penotrations not verified acceptable administrative 1y controlled per OP/0 0/A/6100/14, Penetration Control Daring Modes 5 and 6.
8) The reactor has been suberitical for at least 7 days; or Design Engineering has provided a roouired subcritical time based on plant operating history and actual reduced NCS level.

APPLIC, ABILITY:

Whenever irradiated fuel is in the reactor vessel and NC Syatem wide range level is less than or equal to 16%.

REMEDIAL ACTION:

If any of the above commitments cannot be met during the time that i the reactor vessel is in a reduced inventory condition, take immediate corrective actions to bring the plant into compliance with the COMMITMENT and contact the Station Manager and/or responsible Group Superintendent for additional guidance.

TESTING REQUIREMENTS:

None

REFERENCES:

1) Generic Letter 88-17 (Loss of Decay Heat Removal)
2) NUREG 1410 (Loss of Vital AC Power and Residual Heat Removal 16.5-2 _ __ _ . . _ . _ . _ 11/91 _ _ _ _ _

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during Mid-Loop Operation at Vogtle)

3) Catawba Nuclear Station Directive 3.1.30 (Mid-Loop Operation
4) OP/1(2)/A/6150/06 (Draining the Reactor Coolant System)
5) Catawba Nuclear Station Technical Specificationt
6) Catawba Nuclear Station Technical Specification Interpretations
7) Oconee Nuclear Station selected Licenseo Commitment 16.5.3
8) Integrated Scheduling Management Procedure 3.1 (Outage Planning and Execution Responsibilities)
9) Catawba Nuclear Station responses to Generic Letter 88-17 dated January 3, 1989 BASES:

Generic Letter 88-17 and NUREG 1410 involve concerns associated with a loss of Residual Heat Removal during NC System reduced inventory. Numerous events have occurred in the industry that rusulted in a loss of residual heat removal during reduced inventory operation. This is of great concern due to the potential for substantial core damage occurring in a relatively short tin.e period. This Selected Licensee Commitment depicts those commitments which are extremely important to nuclear safety, however, are not presently covered by Technical Specifications.

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