NLS2020007, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process

From kanterella
Jump to navigation Jump to search

Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems Using the Consolidated Line Item Improvement Process
ML20101H298
Person / Time
Site: Cooper Entergy icon.png
Issue date: 04/01/2020
From: Dent J
Nebraska Public Power District (NPPD)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NLS2020007
Download: ML20101H298 (23)
v • d • e


Text

H Nebraska Public Power District Always there when you need us 50.90 NLS2020007 April 1, 2020 Attention: Document Control Desk U.S. Nuclear Regulatory Commission

. Washington, D.C. 20555-0001

Subject:

Application to Revise Technical Specifications to Adopt TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems" using the Consolidated Line Item Improvement Process Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46

Dear Sir or Madam:

Pursuant to 10 CFR 50.90, Nebraska Public Power District (NPPD) is submitting a request for an amendment to the Technical Specifications (TS) for Cooper Nuclear Station (CNS).

NPPD requests adoption of TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the CNS TS. The proposed amendment revises the TS actions applicable when a residual heat removal shutdown cooling subsystem is inoperable.

Attachment 1 provides a description and assessment of the proposed changes. Attachment 2 provides the existing TS pages marked to show the proposed changes. Attachment 3 provides revised (clean) TS pages. Attachment 4 provides existing TS Bases pages marked to show the proposed changes for information only.

Approval of the proposed amendment is requested by April 1, 2021. Once approved, the amendment shall be implemented within 60 days.

There are no regulatory commitments made in this submittal.

The proposed TS changes have been reviewed by the necessary safety review committees (Station Operations Review Committee and Safety Review and Audit Board). In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," a copy of this application, with attachments, is being provided to the designated State of Nebraska Official.

If you should have any questions regarding this submittal, please contact Linda Dewhirst, Regulatory Affairs and Compliance Manager, at (402) 825-5416.

COOPER NUCLEAR STATION P.O. Box 98 / Brownville, NE 68321-0098 Telephone: (402) 825-3811 / Fax: (402} 825-5211 www.nppd.com

NLS2020007 Page 2 of2 I declare under penalty of perjury that the foregoing is true and correct.

Executed On: -~1-+/-'-1:/~z_o_z_~__

Date Sincerely, l hn Dent, Jr.

Vice President and Chief Nuclear Officer

/dv Attachments: 1. Description and Assessment

2. Proposed Technical Specifications Changes (Mark-up)
3. Revised Technical Specifications Pages
4. Proposed Technical Specifications Bases Changes (Mark-up) -

Information Only cc: Regional Administrator w/ attachments USNRC - Region IV Cooper Project Manager w/ attachments USNRC - NRR Plant Licensing Branch IV Senior Resident Inspector w/ attachments USNRC-CNS Nebraska Health and Human Services w/ attachments Department of Regulation and Li censure NPG Distribution w/o attachments CNS Records w/ attachments

~--------

NLS2020007 Attachment 1 Page 1 of 4 Attachment 1 Description and Assessment Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 1.0 Description 2.0 Assessment 2.1 Applicability of Safety Evaluation 2.2 Variations 3.0 Regulatory Analysis 3.1 No Significant Hazards Consideration Analysis 3 .2 Conclusion 4.0 Environmental Consideration

NLS2020007 Page 2 of 4

1.0 DESCRIPTION

Nebraska Public Power District (NPPD) requests adoption ofTSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the Cooper Nuclear Station (CNS) Technical Specifications (TS). The proposed amendment revises the TS actions applicable when a residual heat removal (RHR) shutdown cooling subsystem is inoperable.

2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation NPPD has reviewed the safety evaluation for TSTF-566 provided to the Technical Specifications Task Force (TSTF) in a letter dated February 21, 2019. This review included a review of the Nuclear Regulatory Commission (NRC) staffs evaluation, as well as the information provided in TSTF-566. NPPD has concluded that the justifications presented in TSTF-566 and the safety evaluation prepared by the NRC staff are applicable to CNS and justify this amendment for the incorporation of the changes to the CNS TS.

2.2 Variations NPPD is proposing the following variations from the TS changes described in TSTF-566 or the applicable parts of the NRC staffs safety evaluation.

The CNS TS utilize different numbering than the Standard Technical Specifications on which TSTF-566 was based. Specifically:

  • Specification 3.4.9, "RHR Shutdown Cooling System -Cold Shutdown" is Specification 3.4.8 in the CNS TS These differences are administrative and do not affect the applicability ofTSTF-566 to the CNS TS.

The traveler discusses the applicable regulatory requirement and guidance, including the 10 CFR 50, Appendix A, General Design Criteria (GDC). CNS was not licensed to the 10 CFR 50, Appendix A, GDC. The CNS equivalent of the GDC is located in Appendix F of the CNS Updated Safety Analysis Report. Specifically, the traveler refers to 10 CFR 50, Appendix A, Criterion 34. CNS does not have an equivalent draft GDC criterion. This difference does not alter the conclusion that the proposed change is applicable to CNS.

NLS2020007 Page 3 of 4

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Analysis Nebraska Public Power District (NPPD) requests adoption ofTSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications, into the Cooper Nuclear Station Technical Specifications (TS).

The proposed amendment revises the TS actions applicable when a residual heat removal (RHR) shutdown cooling subsystem is inoperable.

NPPD has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No The proposed change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The RHR System in the shutdown cooling mode performs the important safety function of removing decay heat from the reactor coolant system during shutdown. The RHR System in the shutdown cooling mode is not an initiator of any accident previously evaluated or assumed to mitigate any accident previously evaluated. The design and function of the RHR System are not affected by the proposed change.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No The proposed change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The proposed change does not affect the design function or operation of the RHR shutdown cooling subsystems. No new equipment is being installed as a result of the proposed change. The proposed change only affects the actions taken when an RHR shutdown cooling subsystem is inoperable, so no new failure mechanisms are created.

NLS2020007 Page 4 of 4 Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No The proposed change revises the actions to be taken when a RHR shutdown cooling subsystem is inoperable. The proposed change does not change any specific values or controlling parameters that define margin in the design or licensing basis. No safety limits are affected by the proposed change. The RHR System in the shutdown cooling mode removes decay heat from the reactor coolant system during shutdown. The proposed change does not affect any design or safety limits associated with the RHR System.

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

Based on the above, NPPD concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

4. ENVIRONMENTAL CONSIDERATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).

Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.

NLS2020007 Page 1 of 5 Attachment 2 Proposed Technical Specifications Changes (Mark-up)

Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages 3.4-15 3.4-16 3.4-18 3.4-19

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES---------------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
2. One RHR shutdown cooling subsystem may be inoperable for up to 2 liours for the performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure less than the shutdown cooling permissive pressure.

ACTIONS

  • -------------NOTE---------------

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 lflitiate aetien te resteFe Iffilflediately cooling subsystems RHR sht:1tdert1fl eoolifl~

inoperable. s~esystel'ltEs~ te OPERABLE statt:1s.

All.In

,coRtii:iued)

Cooper 3.4-15 Amendment No. z6S-

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (eeAtiFttJed) Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of decay heat removal is available for each B. Required Action 8.1 Initiate action inoperable RHR shutdown Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and associated cooling subsystem.

to restore RH R thereafter Completion Time of shutdown cooling Condition A not subsystem(s) to met. OPERABLE status. 24 l'iettFS Immediately No RHR shutdown cooling Initiate action to restore Immediately subsystem in operation. one RHR shutdown

. cooling subsystem or one AND recirculation pump to operation.

No recirculation pump in operation.

Verify reactor coolant 1 hourfrom circulation by an alternate discovery of no method. reactor coolant circulation Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter Monitor reactor coolant Once per hour temperature and pressure.

Cooper 3.4-16 Amendment No.~

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS}

3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES--------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.

APPLICABILITY: MODE 4.

ACTIONS

NOTE --------

Separate Condition entry is allowed for each shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each ANO inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and associated 8.1 Initiate action to Completion Time of restore RHR shutdown Condition A not met. cooling subsystem(s) to Immediately OPERABLE status.

Cooper 3.4-18 Amendment No.~

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS {continued)

CONDITION REQUIRED ACTION COMPLETION TIME

--8:- No RHR shutdown cooling .4- Verify reactor coolant 1 hourfrom subsystem in operation. circulating by an alternate discovery of no method. reactor AND coolant circulation 1

No recirculation pump in operation.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter

--8-:2- Monitor reactor coolant Once per hour

\ temperature.

....i........ :=""IIC.2 Ii----- ----=- -------

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR shutdown cooling subsystem or In accordance with recirculation pump Is operating. the Surveillance Frequency Control Program Cooper 3.4-19 Amendment No. -265-

NLS2020007 Page 1 of 5 Attachment 3 Revised Technical Specifications Pages Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages 3.4-15 3.4-16 3.4-18 3.4-19

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS)

. 3.4. 7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES-------------------------------------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.

APPLICABILITY: MODE 3, with reactor steam dome pressure less than the shutdown cooling permissive pressure.

ACTIONS

NOTE------------------------------------------------------------

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter (continued)

Cooper 3.4-15 Amendment No.

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Initiate action to restore Immediately associated Completion Time RHR shutdown cooling of Condition A not met. subsystem(s) to OPERABLE status.

C. No RHR shutdown cooling C.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem or one AND recirculation pump to operation.

No recirculation pump in operation. AND C.2 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from circulation by an alternate discovery of no method. reactor coolant circulation AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.3 Monitor reactor coolant Once per hour temperature and pressure.

Cooper 3.4-16 Amendment No.

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

NOTES-------------------------------------------

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period.
2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the performance of Surveillances.

APPLICABILITY: MODE 4.

ACTIONS

*----------------------NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A One or two RHR shutdown A.1 Verify.an alternate method 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cooling subsystems of decay heat removal is inoperable. available for each AND inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter B. Required Action and 8.1 Initiate action to restore

(continued)

Cooper 3.4-18 Amendment No.

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. No RHR shutdown cooling C. 1 Verify reactor coolant 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from subsystem in operation. circulating by an alternate discovery of no method. reactor AND coolant circulation No recirculation pump in AND operation.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR shutdown cooling subsystem or In accordance with recirculation pump is operating. the Surveillance Frequency Control Program Cooper 3.4-19 Amendment No.

NLS2020007 Page 1 of7 Attachment 4 Proposed Technical Specifications Bases Changes (Mark-up) -

Information Only Cooper Nuclear Station, Docket No. 50-298, License No. DPR-46 Revised Pages B 3.4-36 B 3.4-37 B 3.4-42 B 3.9-24 B 3.9-29 Note: Attachment includes page of Bases Inserts

i--

1 NLS2020007 Attachment 4 Page 2 of7 Bases Inserts Insert 1 (B 3.4.7 Required Action A.l)

Furthermore, verification of the functional availability of these alternate method(s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.

Insert 2 (B 3.4.7 and B 3.4.8 new Required Action B.1)

If the required alternate method(s) of decay heat removal cannot be verified within one hour, immediate action must be taken to restore the inoperable RHR shutdown cooling subsystem(s) to operable status. The Required Action will restore redundant decay heat removal paths. The immediate Completion Time reflects the importance of maintaining the availability of two paths for heat removal.

Insert 3 (B 3.9.7 and B 3.9.8 Required Action A.l)

The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Spent Fuel Pool Cooling System, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS

\

A Note has been provided to modify the ACTIONS related to RHR shutdown cooling subsystems. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition. Section 1.3 also specifies Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for inoperable shutdown cooling subsystems provide appropriate compensatory measures for separate inoperable shutdown cooling subsystems. As such, a Note has been provided that allows separate Condition entry for each inoperable RHR shutdown cooling subsystem.

A.1, A.2, anel A.3 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the inopei:ael~

sybsystem mi.n;:;t ber:ester:ed te OPERA.BU: sta&is withe1:1t eelay. In this sensitien, the r:smaining O~ERABbE s1:1bsystaFR saA pFO'Jiae tl=le nesm;sary desay heat FOmoval. Tho overall reliability is reduced, ha'll*ve'Jef; because a single failure in the OPERABLE subsystem could result in reduced RHR shutdown cooling capability. Therefore, an alternate method of decay heat removal must be provided.

With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial RHR shutdown cooling subsystem inoperability.

This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available.--_ _ ___,

decay heat removal capabilities. -<  ![INSERT 1] I sufficient to The required cooling capacity of the alternate method should be ensured by '.°'Orifying (by ealeulation or deFAanstratien) its eapabilit)* to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability.

Alternate methods that can be used include (but are not limited to) the Condensate/Main Steam Systems, the Reactor Water Cleanup System,

~ a combination of an ECCS pump and a safetv/relief valve... .... ,,

, or an inoperable but functional RHR Hows\rer, d1:10 te the potentially rsel1:1oeel FOliability of the alternate shutdown cooling ~ Y heammsval, it is also me;1:1ir0el te meh,1se tho master system. soolimt tompemt1:1m te the point 'NReFS MODE 4 iG entorsel.

[INSERT 2]

Cooper B 3.4-36 1211e119 I

RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 BASES ACTIONS (continued)

C.1, C.2, and C.3 B.1, 8.2. and B.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or recirculation pump must be restored without delay.

Until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature.

The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.

During the period when the reactor cool~nt is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLAN CE REQUIREMENTS SR 3.4.7.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant. The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

This Surveillance is modified by a Note allowing sufficient time to align the RHR System for shutdown cooling operation after clearing the pressure interlock that isolates the system, or for placing a recirculation pump in operation. The Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is not required for this initial 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period), which also allows entry into the Applicability of this Specification in accordance with SR 3.0.4 since the Surveillance will not be "not met" at the time of entry into the Applicability.

Cooper B 3.4-37 12119119 I

RHR Shutdown Cooling Syst~~~Cold Shutdown

..- B 3.4.8 BASES ACTIONS A.:.l (continued)

Therefore, an alternate method of decay heat removal must be provided. With both RHR shutdown cooling subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided 'for the initial RHR shutdown cooling subsystem inoperability. This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The l hour Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of these alternate method{s) must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will provide assurance of continued heat removal capability.

The required cooling capacity of the alternate method should

~ . be eRsureEI l3:Y verifyiR§ (l:ly ealculatieR er ElemeRstratieR)

~ its Gapability to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include {but are not limited to) the Reactor Water Cleanup S~ystem -aft&-a combination of an

~ ECCS pump and a safety/relief v ve r-------------,

~ ~ , , or an inoperable but

:?" IL 1 aRe B.2 functional RHR shutdown

[ cooling subsystem

!C.1 and C.2 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the coolant circulation function and is modified such that the I hour is applicable separately for each occurrence involving a loss of coolant circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. This will provide assurance of continued temperature monitoring capability.

During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown cooling subsystem or recirculation pump), the reactor coolant temperature and pressure must be (continued)

Cooper B 3.4-42 Revisia~ 9

RHR-ttigh Water Level B 3.9.7 BASES ACTIONS A.l (continued) heat from the reactor core. However, the overall reliability is reduced because loss of water level could result in reduced decay heat removal capability. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of the alternate method must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will ensure continued heat removal capability.

Alternate decay heat removal methods are available to the operators for review and preplanning in the unit Operating Procedures. T~e req1:1ired caaliA§ ca13acity af the alterAate met Ras sha1:1hi be 0Rs1:1red b;Y veri fyi R§ ( by cal c1:1l at i aR er aeffionstra.tion) its eap-ability to mailitaiii or 1ed~e@

tem13erat1:1re. Far exam13l e, tk is may i Acl 1:1cle tke use af H ~

~ S13eRt Fwel Peal Gaal iR§ Systeffl aRa tl:ie Reactar Water Cl eaR1:113

£ystem, a13eratiR§ wit~ tRe regeRerative ~eat cxchaAger by13assed er iR cembiRatiaR with the CeRtral Rea Drive System or (QRQ(Ul&aie System... The method used to remove the decay heat should be the most prudent choice based on station conditions.

8.1, 8.2, B.3, and B.4 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.l, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending loading of irradiated fuel assemblies into the RPV.

Additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases {i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative cont~ols to assure isolation capability.

These administrative controls consist of stationing an (continued)

Cooper B 3.9-24 RevisiaA O

RHR~Low Water Level B 3.9.8 BASES ACTIONS A.1 (continued}

LCO. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is based on the decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore, verification of the functional availability of this alternate method must be reconfirmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter. This will ensure continued heat removal capability.

Alternate decay heat removal methods are available to the operators for review and preplanning in the unit Operating Procedures. +ltt: required eeel i Ag capacity af the alterAate

![INSERT 3] methaa shaYlel ae eRs1:noea l:Jy \,'el"ifyiRg (l:Jy calc1:.1latieA er ElemaAstratisR) its ca~aeity ts maiAtaiflSr iceel1:.1ce tem~el"at1:.1re. Fsr exam~le, this may iRcl1:.1de tRe ~se ef tRe SpeAt F~el Peel CeeliA§ System aAa the Reacter Water GleaRUf.)

Systeffl, ef.)erati Ag \~i th Uie re§eiterati ve heat e~ckafl~

byf.)a-s-s-ea er i 1, cemai 1,ati Sl'I with the CaRtral Rael Drive System--

er CsRseRsate ~ystem, The method used to remove decay heat should be the most prudent choice based on station conditions.

B.1, B.2, and 8.3 With the required decay heat removal subsystem(s} inoperable and the required alternate method(s} of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.

These administrative controls consist of stationing an operator, who is in continuous communication with the control room, at the controls of the isolation device. In this way, the penetration can be rapidly isolated when a need for secondary containment is indicated.} This may be performed as an administrative check, by examining logs or (continued}

Cooper B 3.9-29 Revisiefl 0

Retrieved from "https://kanterella.com/w/index.php?title=NLS2020007,_Application_to_Revise_Technical_Specifications_to_Adopt_TSTF-566,_Revise_Actions_for_Inoperable_RHR_Shutdown_Cooling_Subsystems_Using_the_Consolidated_Line_Item_Improvement_Process&oldid=3482074"