Text

Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
	ML23145A086
Person / Time
Site:	Dresden, Peach Bottom, Nine Mile Point, Clinton, Quad Cities, FitzPatrick, LaSalle
Issue date:	05/25/2023
From:	Simpson P; Constellation Energy Generation
To:	; Office of Nuclear Reactor Regulation, Document Control Desk
References
	RS-23-042
	Download: ML23145A086 (1)
	v • d • e

4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office RS-23-042 10 CFR 50.90 May 25, 2023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 NRC Docket No. 50-410 Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos.50-277, and 50-278 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Application to Revise Technical Specifications to Adopt TSTF-580, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling"

Reference:

Letter from N. J. Jordan (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluations of Technical Specifications Task Force Traveler TSTF-580, Revision 1, 'Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling.'" dated July 11, 2021

May 25, 2023 U.S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed FOL No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2, Subsequent Renewed FOL Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRC-approved Industry/Technical Specifications Task Force Traveler 580 (TSTF-580), Revision 1, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling."

provides the evaluation for the proposed changes. Attachment 2 provides the existing TS pages marked up depicting the proposed changes. Attachment 3 provides retyped TS pages. Attachment 4 provides the existing TS Bases marked up depicting the proposed changes (for information only).

The proposed changes have been reviewed and approved by the Plant Operations Review Committee at each station in accordance with the requirements of the CEG Quality Assurance Program.

CEG requests approval of the proposed changes by May 27, 2024. Once approved, the amendment shall be implemented within 60 days.

In accordance with 10 CFR 50.91, "Notice for public comment; State consultation,"

paragraph (b), CEG is notifying the State of Illinois, the State of New York, the State of Pennsylvania, and the State of Maryland of this application for license amendment by transmitting a copy of this letter and its attachments to the designated State Officials.

May 25, 2023 U.S. Nuclear Regulatory Commission Page 3 There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mrs. Linda M. Palutsis at (630) 657-2821.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 25th day of May 2023.

Respectfully, Patrick R. Simpson Sr. Manager Licensing Constellation Energy Generation, LLC Attachments:

1. Evaluation of Proposed Changes

2. Proposed TS - Marked-Up Pages

3. Retyped TS Pages

4. Markup of Proposed Technical Specifications Bases Pages (For Information Only) cc:

NRC Regional Administrator, Region I NRC Regional Administrator, Region III NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - James A. FitzPatrick Nuclear Power Plant NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Nine Mile Point Nuclear Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety A. L. Peterson, NYSERDA R. R. Janati, Pennsylvania Bureau of Radiation Protection D. Tancabel, State of Maryland

ATTACHMENT 1 Evaluation of Proposed Changes Page 1 of 5 1.0

SUMMARY

DESCRIPTION In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed FOL No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2, Subsequent Renewed FOL Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRC-approved Industry/Technical Specifications Task Force Traveler 580 (TSTF-580), Revision 1, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications (TS) exception to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.

2.0 DETAILED DESCRIPTION 2.1 Applicability of Safety Evaluation CEG has reviewed the safety evaluation for TSTF-580 provided to the Technical Specifications Task Force in a letter dated July 11, 2021 (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-580 (Reference 1). As described below, CEG has concluded that the justifications presented in TSTF-580 and the safety evaluation prepared by the NRC are applicable to Clinton Power Station, Unit 1, Dresden Nuclear Power Station, Units 2 and 3, James A. FitzPatrick Nuclear Power Plant, LaSalle County Station, Units 1 and 2, Nine Mile Point Nuclear Station, Unit 2, Peach Bottom Atomic Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.

2.2 Variations Some CEG plants TS utilize different numbering than the Standard TS on which TSTF-580 was based (Reference 3 and 4). The specific differences between the plant TS and TSTF-580 are described in Table 1. These differences are administrative and do not affect the applicability of TSTF-580 to the CEG plants TS.

ATTACHMENT 1 Evaluation of Proposed Changes Page 2 of 5 Table 1. Specific Differences Between CEG TS and TSTF-580 (NUREG-1433)

TSTF-580 (NUREG-1433)

Dresden Variations FitzPatrick Variations Peach Bottom Variations Quad Cities Variations 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System -

Hot Shutdown Numbering and title difference 3.4.7 Shutdown Cooling (SDC)

SystemHot Shutdown Numbering difference 3.4.7 Numbering difference 3.4.7 Numbering difference 3.4.7 3.4.8 CONDITION E, REQUIRED ACTIONS E.1, E.2, and E.3 None No corresponding CONDITION.

None CONDITION and REQUIRED ACTIONS numbering and formatting difference 3.4.7 CONDITION A REQUIRED ACTIONS A.2 and A.3 Note: No differences were identified between NUREG-1434 and plant TS (i.e., Clinton, LaSalle, and Nine Mile Point 2)

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Analysis In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Constellation Energy Generation, LLC (CEG), requests an amendment to Facility Operating License (FOL) No. NPF-62 for Clinton Power Station, Unit 1, Renewed FOL Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station, Units 2 and 3, Renewed FOL No. DPR-59 for James A. FitzPatrick Nuclear Power Plant, Renewed FOL Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, Renewed FOL No. NPF-69 for Nine Mile Point Nuclear Station, Unit 2, Subsequent Renewed FOL Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station, Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2. The proposed amendment is consistent with previously NRC-approved Industry/Technical Specifications Task Force Traveler 580 (TSTF-580), Revision 1, "Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling." The proposed change provides a Technical Specifications (TS) exception

ATTACHMENT 1 Evaluation of Proposed Changes Page 3 of 5 to entering Mode 4 if both required Residual Heat Removal (RHR) shutdown cooling subsystems are inoperable.

CEG has evaluated the proposed change against the criteria of 10 CFR 50.92(c) to determine if the proposed change results in any significant hazards. The following is the evaluation of each of the 10 CFR 50.92(c) criteria:

1.

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

Response: No The proposed change provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are 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.

The proposed change would also exempt entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable and other operating modes of the RHR System are inoperable, such as Low Pressure Core Injection (LPCI) and RHR suppression pool cooling, and both subsystems of the support system for the RHR System heat exchangers, the RHR Service Water (RHRSW) System, are inoperable.

The TS for those RHR operating modes and the RHRSW System require entering Mode 4 when both required subsystems are inoperable. Those operating modes and systems are not initiators to any accident previously evaluated but are used to mitigate the consequences of an accident previously evaluated. However, the consequences of an accident previously evaluated resulting from remaining in Mode 3 versus Mode 4 when RHR shutdown cooling subsystems are inoperable are not significantly increased because there would be no dependable method to remove post-accident decay heat in Mode 4 if both required RHR shutdown cooling subsystems are inoperable.

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

2.

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

Response: No The proposed change provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are inoperable. The proposed change does not affect the design function or operation of the RHR System or the RHRSW System. No new equipment is being installed as a result of the proposed change. The proposed change affects the actions taken when both required RHR shutdown cooling subsystems are inoperable, so no new failure mechanisms are created.

ATTACHMENT 1 Evaluation of Proposed Changes Page 4 of 5 Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.

3.

Does the proposed change involve a significant reduction in a margin of safety?

Response: No The proposed change provides a TS exception to entering Mode 4 if both required RHR shutdown cooling subsystems are 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 proposed change applies when both required RHR shutdown cooling subsystems are inoperable, so no design or safety limits associated with the operation of the RHR System are affected.

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

Based on the above, CEG concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and complies with the "generic" determination in 10 CFR 50.75(h)(4), accordingly, a finding of "no significant hazards consideration" is justified.

3.2 Conclusions 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.

4.0 ENVIRONMENTAL EVALUATION The proposed amendment involves (i) changes to surety, insurance, and/or indemnity requirements, or (ii) changes to recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b),

no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

ATTACHMENT 1 Evaluation of Proposed Changes Page 5 of 5

5.0 REFERENCES

1.

Letter from the Technical Specifications Task Force to the U.S. Nuclear Regulatory Commission, "Transmittal of TSTF-580, Revision 1, 'Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling,'" dated January 26, 2021

2.

Letter from N. J. Jordan (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluations of Technical Specifications Task Force Traveler TSTF-580, Revision 1,

'Provide Exception from Entering Mode 4 With No Operable RHR Shutdown Cooling.'"

dated July 11, 2021

3.

NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 5, dated September 2021

4.

NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants, Volume 1, Revision 5, dated September 2021

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4-22 3.4-23

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-22 Amendment No. 236 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.9 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut in 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 cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion time of Condition A not met.

B.1 Initiate action to restore RHR Shutdown Cooling subsystem(s) to OPERABLE status.

Immediately (continued)

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-23 Amendment No. 236 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

No RHR shutdown cooling subsystem in operation.

AND C.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

Immediately No recirculation pump in operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.3 Monitor reactor coolant temperature and pressure.

Once per hour SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control program (continued)

E.

E.1 E.2 E.3

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1 3.4.7-2

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-1 Amendment No. 274/267 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Shutdown Cooling (SDC) SystemHot Shutdown LCO 3.4.7 Two SDC subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one SDC subsystem shall be in operation.

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

1.

Both required SDC subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required SDC subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor vessel coolant temperature less than the SDC cut-in permissive temperature.

ACTIONS

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

Separate Condition entry is allowed for each SDC subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required SDC subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable required SDC subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-2 Amendment No. 274/267 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required SDC subsystem(s) to OPERABLE status.

Immediately C. No required SDC subsystem in operation.

AND No recirculation pump in operation.

C.1 Initiate action to restore one required SDC subsystem or one recirculation pump to operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

AND C.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour E.

E.1 E.2 E.3

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 JAFNPP 3.4.7-1 Amendment 340 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.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR cut in 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 cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.9-1 3.4.9-2

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-1 Amendment No. 248/234 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.9 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 not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor vessel pressure less than the RHR cut-in 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 cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-2 Amendment No. 248/234 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

AND C.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour E.

E.1 E.2 E.3

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.5 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.9-1 3.4.9-2

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-1 Amendment 91, 109, 185 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.9 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 not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut-in 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 cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-2 Amendment 91, 185 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

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

Immediately C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

AND C.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour E.

E.1 E.2 E.3

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.6 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 REVISED TECHNICAL SPECIFICATIONS PAGES Peach Bottom Atomic Power Station, Unit 2 3.4-16 3.4-17 Peach Bottom Atomic Power Station, Unit 3 3.4-16 3.4-17

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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each required inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 2 3.4-16 Amendment/P337

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

AND C.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour PBAPS UNIT 2 3.4-17 Amendment No. 337 E.

E.1 E.2 E.3

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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each required inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 3 3.4-16 Amendment No. 340

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time of condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately C. No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND C.2 Verify reactor coolant circulation by an alternate method.

AND C.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour PBAPS UNIT 3 3.4-17 Amendment No. 340 E.

E.1 E.2 E.3

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.7 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1 3.4.7-2

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-1 Amendment No. 286/282 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR cut-in 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 cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-2 Amendment No. 286/282 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

AND A.2

NOTE--------

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Verify reactor coolant circulation by an alternate method.

AND A.3

NOTE--------

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Monitor reactor coolant temperature and pressure.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately Insert QC

Insert QC C. Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

ATTACHMENT 3 Retyped Technical Specifications Pages 3.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4-22 3.4-23 3.4-24

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-22 Amendment No. 236 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System Hot Shutdown LCO 3.4.9 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion time of Condition A not met.

B.1 Initiate action to restore RHR Shutdown Cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-23 Amendment No.

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately E.

No RHR shutdown cooling subsystem in operation.

AND E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

Immediately No recirculation pump in operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND E.3 Monitor reactor coolant temperature and pressure.

Once per hour

RHR Shutdown Cooling System Hot Shutdown 3.4.9 CLINTON 3.4-24 Amendment No. 236 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control program

ATTACHMENT 3 Retyped Technical Specifications Pages 3.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1 3.4.7-2 3.4.7-3 3.4.7-4

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-1 Amendment No. 274/267 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Shutdown Cooling (SDC) SystemHot Shutdown LCO 3.4.7 Two SDC subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one SDC subsystem shall be in operation.

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

1.

Both required SDC subsystems and recirculation pumps may be not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required SDC subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor vessel coolant temperature less than the SDC cut-in permissive temperature.

ACTIONS

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

Separate Condition entry is allowed for each SDC subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required SDC subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-2 Amendment No. 274/267 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required SDC subsystem to OPERABLE status.

Immediately C. Two required SDC subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable SDC subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D. Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one required SDC subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one SDC subsystem to OPERABLE status.

Immediately (continued)

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-3 Amendment No. 274/267 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

No required SDC subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one required SDC subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

SDC System Hot Shutdown 3.4.7 Dresden 2 and 3 3.4.7-4 Amendment No.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor vessel coolant temperature is less than the SDC cut-in permissive temperature.

Verify one SDC subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.7.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor vessel coolant temperature is less than the SDC cut-in permissive temperature.

Verify SDC subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program

ATTACHMENT 3 Retyped Technical Specifications Pages 3.3 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1 3.4.7-2

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 JAFNPP 3.4.7-1 Amendment 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.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR cut in permissive pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 JAFNPP 3.4.7-2 Amendment ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut in permissive pressure.

Verify each required RHR shutdown cooling subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, is in the correct position, or can be aligned to the correct position.

In accordance with the Surveillance Frequency Control Program

ATTACHMENT 3 Retyped Technical Specifications Pages 3.4 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4.9-1 3.4.9-2 3.4.9-3 3.4.9-4

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-1 Amendment No. 248/234 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.9 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 not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor vessel pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-2 Amendment No. 248/234 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C. Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D. Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-3 Amendment No. 214/200 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

RHR Shutdown Cooling SystemHot Shutdown 3.4.9 LaSalle 1 and 2 3.4.9-4 Amendment No.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor vessel pressure is less than the RHR cut-in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program

ATTACHMENT 3 Retyped Technical Specifications Pages 3.5 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4.9-1 3.4.9-2 3.4.9-3 3.4.9-4

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-1 Amendment 91, 109, 185185 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.9 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 not in operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3 with reactor steam dome pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-2 Amendment 91, 185185 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of Condition A not met B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-3 Amendment 91, 185185 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 NMP2 3.4.9-4 Amendment 91, 150, 152 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program SR 3.4.9.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR cut-in permissive pressure.

Verify RHR shutdown cooling subsystem Locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program

ATTACHMENT 3 Retyped Technical Specifications Pages 3.6 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 RETYPED TECHNICAL SPECIFICATIONS PAGES Peach Bottom Atomic Power Station, Unit 2 3.4-16 3.4-17 3.4-18 3.4-19 3.4-20 3.4-21 3.4-22 3.4-23 3.4-24 3.4-25 3.4-26 3.4-27 3.4-28 3.4-29 Peach Bottom Atomic Power Station, Unit 3 3.4-16 3.4-17 3.4-18 3.4-19 3.4-20 3.4-21 3.4-22 3.4-23 3.4-24 3.4-25 3.4-26 3.4-27 3.4-28 3.4-29

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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 2 3.4-16 Amendment No. 337

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

PBAPS UNIT 2 3.4-17 Amendment No. 337 CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem to OPERABLE status.

Immediately C. Two required RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D. Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately

PBAPS UNIT 2 3.4-18 Amendment No. 337 RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

RHR Shutdown Cooling System Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.7.2

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

1.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

2.

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-19 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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 4.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately (continued)

PBAPS UNIT 2 3.4-20 Amendment No.

RHR Shutdown Cooling System Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Verify reactor coolant circulating by an alternate method.

AND C.2 Monitor reactor coolant temperature and pressure.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.8.2

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

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-21 Amendment No.

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE--------

Required Action A.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in MODE 1, 2, or 3.

A.1 Restore parameter(s) to within limits.

AND A.2 Determine RCS is acceptable for continued operation.

30 minutes 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

PBAPS UNIT 2 3.4-22 Amendment No.

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE---------

Required Action C.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in other than MODES 1, 2, and 3.

C.1 Initiate action to restore parameter(s) to within limits.

AND C.2 Determine RCS is acceptable for operation.

Immediately Prior to entering MODE 2 or 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a.

RCS pressure and RCS temperature are within the limits specified in the PTLR; and b.

RCS heatup and cooldown rates are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

(continued)

PBAPS UNIT 2 3.4-23 Amendment No.

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within the criticality limits specified in the PLTR.

Once within 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom head coolant temperature and the reactor pressure vessel (RPV) coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.4

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump (continued)

PBAPS UNIT 2 3.4-24 Amendment No.

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5

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

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.6

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

Not required to be performed until 30 minutes after RCS temperature 80°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.7

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature 100°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-25 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-26 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-27 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 2 3.4-28 Amendment No.

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 1053 psig.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 1053 psig.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 2 3.4-29 Amendment No.

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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR shutdown cooling isolation pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One required RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

PBAPS UNIT 3 3.4-16 Amendment No. 340

RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required Action and associated Completion Time of condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem to OPERABLE status.

Immediately C.

Two required RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

D.

Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

DC.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately (continued)

PBAPS UNIT 3 3.4-17 Amendment No. 340

PBAPS UNIT 3 3.4-18 Amendment No. 337 RHR Shutdown Cooling System Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

RHR Shutdown Cooling System Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.7.2

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

1.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is less than the RHR shutdown cooling isolation pressure.

2.

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-19 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 required RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for performance of Surveillances.

APPLICABILITY:

MODE 4.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR shutdown cooling subsystems inoperable.

A.1 Verify an alternate method of decay heat removal is available for each inoperable required RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore required RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately (continued)

PBAPS UNIT 3 3.4-20 Amendment No.

RHR Shutdown Cooling System Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

C.1 Verify reactor coolant circulating by an alternate method.

AND C.2 Monitor reactor coolant temperature and pressure.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.8.2

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

HPSW system related components are excluded.

Verify required RHR shutdown cooling subsystem locations susceptible to gas accumulation are sufficiently filled with water.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-21 Amendment No.

RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within the limits specified in the PTLR.

APPLICABILITY:

At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

NOTE---------

Required Action A.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in MODE 1, 2, or 3.

A.1 Restore parameter(s) to within limits.

AND A.2 Determine RCS is acceptable for continued operation.

30 minutes 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B.

Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours (continued)

PBAPS UNIT 3 3.4-22 Amendment No.

RCS P/T Limits 3.4.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

NOTE---------

Required Action C.2 shall be completed if this Condition is entered.

Requirements of the LCO not met in other than MODES 1, 2, and 3.

C.1 Initiate action to restore parameter(s) to within limits.

AND C.2 Determine RCS is acceptable for operation.

Immediately Prior to entering MODE 2 or 3.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1

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

Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

Verify:

a.

RCS pressure and RCS temperature are within the limits specified in the PTLR; and b.

RCS heatup and cooldown rates are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

(continued)

PBAPS UNIT 3 3.4-23 Amendment No.

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.2 Verify RCS pressure and RCS temperature are within the criticality limits specified in the PTLR.

Once within 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the bottom head coolant temperature and the reactor pressure vessel (RPV) coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump SR 3.4.9.4

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

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump start.

Verify the difference between the reactor coolant temperature in the recirculation loop to be started and the RPV coolant temperature is within the limits specified in the PTLR.

Once within 15 minutes prior to each startup of a recirculation pump (continued)

PBAPS UNIT 3 3.4-24 Amendment No.

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5

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

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.6

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

Not required to be performed until 30 minutes after RCS temperature 80°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

SR 3.4.9.7

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature 100°F in MODE 4.

Verify reactor vessel flange and head flange temperatures are within the limits specified in the PTLR.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-25 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-26 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-27 Amendment No.

THE INFORMATION ON THIS PAGE HAS BEEN DELETED.

INTENTIONALLY LEFT BLANK.

PBAPS UNIT 3 3.4-28 Amendment No.

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 1053 psig.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Reactor steam dome pressure not within limit.

A.1 Restore reactor steam dome pressure to within limit.

15 minutes B.

Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 1053 psig.

In accordance with the Surveillance Frequency Control Program.

PBAPS UNIT 3 3.4-29 Amendment No.

ATTACHMENT 3 Retyped Technical Specifications Pages 3.7 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 RETYPED TECHNICAL SPECIFICATIONS PAGES 3.4.7-1 3.4.7-2

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-1 Amendment No. 286/282 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling SystemHot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE.

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

One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY:

MODE 3, with reactor steam dome pressure less than the RHR cut-in permissive pressure.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR shutdown cooling subsystem inoperable.

A.1 Verify an alternate method of decay heat removal is available.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

Immediately C. Two RHR shutdown cooling subsystems inoperable.

C.1 Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

(continued)

RHR Shutdown Cooling SystemHot Shutdown 3.4.7 Quad Cities 1 and 2 3.4.7-2 Amendment No. 286/282 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition C not met.

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

LCO 3.0.3 and all other LCO Required Actions requiring a MODE change to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status.

D.1 Initiate action to restore one RHR shutdown cooling subsystem to OPERABLE status.

Immediately E. No RHR shutdown cooling subsystem in operation.

AND No recirculation pump in operation.

E.1 Initiate action to restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

AND E.2 Verify reactor coolant circulation by an alternate method.

AND E.3 Monitor reactor coolant temperature and pressure.

Immediately 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4-46 B 3.4-47

RHR Shutdown Cooling System Hot Shutdown B 3.4.9 CLINTON B 3.4-46 Revision No. 21-5 BASES ACTIONS A.1 (continued)

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 methods must be confirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capacity.

The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature at or below 200F. 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 System, or an inoperable but functional RHR shutdown cooling subsystem.

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.

C.1, C.2, and C.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as is permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or one 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. This will provide assurance of continued temperature monitoring capability.

(continued)

E.1, E.2, and E.3 INSERT 1

Insert 1 C.1 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

RHR Shutdown Cooling System Hot Shutdown B 3.4.9 CLINTON B 3.4-47 Revision No. 21-5 BASES ACTIONS C.1, C.2, and C.3 (continued)

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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.9.1 REQUIREMENTS 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

SR 3.4.9.2 RHR Shutdown Cooling System piping and components have the potential to develop voids and pockets of entrained gases.

Preventing and managing gas intrusion and accumulation is necessary for proper operation of the RHR shutdown cooling subsystems and may also prevent water hammer, pump cavitation, and pumping of noncondensible gas into the reactor vessel.

Selection of RHR Shutdown Cooling System locations susceptible to gas accumulation is based on a review of system design information, including piping and instrumentation drawings, isometric drawings, plan and elevation drawings, and calculations. The design review is supplemented by system walk downs to validate the system high points and to confirm the location and orientation of important components that can become sources of gas or could otherwise cause gas to be trapped or difficult to remove (continued)

E.1, E.2, and E.3

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.2 Dresden Nuclear Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4.7-3 B 3.4.7-4 B 3.4.7-5

SDC SystemHot Shutdown B 3.4.7 Dresden 2 and 3 B 3.4.7-3 Revision 85 BASES APPLICABILITY The requirements for decay heat removal in MODES 4 and 5 are (continued) discussed in LCO 3.4.8, "Shutdown Cooling (SDC) SystemCold Shutdown"; LCO 3.9.8, "Shutdown Cooling (SDC)High Water Level"; and LCO 3.9.9, "Shutdown Cooling (SDC)Low Water Level."

ACTIONS A Note has been provided to modify the ACTIONS related to SDC 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 SDC subsystem.

A.1 With one required SDC subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced because a single failure in the OPERABLE subsystem could result in reduced SDC capability.

Therefore, an alternate method of decay heat removal must be provided.

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

This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

(continued)

SDC SystemHot Shutdown B 3.4.7 Dresden 2 and 3 B 3.4.7-4 Revision 85 BASES ACTIONS A.1 (continued)

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), or an inoperable but functional SDC subsystem.

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 SDC subsystems(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.

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

Until SDC 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter. This will provide assurance of continued temperature monitoring capability.

(continued)

E.1, E.2, and E.3 Insert 2

Insert 2 C.1 With both required SDC subsystems inoperable, an alternate method of decay heat removal must be provided in addition to that provided for the initial SDC subsystem inoperability. This re-establishes backup decay heat removal capabilities, similar to the requirements of the LCO. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Feed and Main Steam Systems, the Reactor Cleanup System (by itself or using feed and bleed in combination with Control Rod Drive System or Condensate/Feed System), or an inoperable but functional SDC subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one SDC subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one SDC subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the SDC subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available. When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

SDC SystemHot Shutdown B 3.4.7 Dresden 2 and 3 B 3.4.7-5 Revision 85 BASES ACTIONS C.1, C.2, and C.3 (continued)

During the period when the reactor coolant is being circulated by an alternate method (other than by the required SDC 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.

SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one SDC 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 SDC 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

SR 3.4.7.2 SDC System piping and components have the potential to develop voids and pockets of entrained gases. Preventing and managing gas intrusion and accumulation is necessary for proper operation of the SDC subsystems and may also prevent water hammer, pump cavitation, and pumping of noncondensible gas into the reactor vessel.

Selection of SDC System locations susceptible to gas accumulation is based on a review of system design information, including piping and instrumentation drawings, isometric drawings, plan and elevation drawings, and calculations. The design review is supplemented by system (continued)

E.1, E.2, and E.3

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.3 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4.7-3 B 3.4.7-4

RCS Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES JAFNPP B 3.4.7-3 Revision 48 The requirements for decay heat removal in MODES 4 and 5 are discussed in LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown; LCO 3.9.7, Residual Heat Removal (RHR) - High Water Level"; and LCO 3.9.8, "Residual Heat Removal (RHR) - Low Water Level."

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 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by the LCO Note, the overall reliability is reduced, however, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 (continued)

APPLICABILITY (continued)

RCS Shutdown Cooling System - Hot Shutdown B 3.4.7 BASES JAFNPP B 3.4.7-4 Revision 48 method capability. Alternate methods that can be used include (but are not limited to) the Condensate and Main Steam Systems, Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate System), or a combination of an RHR pump and safety/relief valve(s),

or an inoperable but functional RHR shutdown cooling subsystem..

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.

SURVEILLANCE REQUIREMENTS SR 3.4.7.1 Verifying the correct alignment for manual, power operated, and automatic valves in the RHR shutdown cooling flow path provides assurance that the proper flow paths will exist for RHR operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. A valve that can be manually (from the control room or locally) aligned is allowed to be in a non-RHR shutdown cooling position provided the valve can be repositioned. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

This Surveillance is modified by a Note allowing sufficient time to verify RHR shutdown cooling subsystem OPERABILITY after clearing the pressure interlock that isolates the system. The Note takes exception to the requirements of the Surveillance being met (i.e.,

valves are aligned or can be aligned is not required for this initial 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

ACTION (continued)

(continued)

Insert 3

Insert 3 C.1 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate and Main Steam Systems, Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate System), or a combination of an RHR pump and safety/relief valve(s), or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.4 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4.9-3 B 3.4.9-4 B 3.4.9-5

RHR Shutdown Cooling SystemHot Shutdown B 3.4.9 LaSalle 1 and 2 B 3.4.9-3 Revision 87 BASES APPLICABILITY The requirements for decay heat removal in MODES 4 and 5 are (continued) discussed in LCO 3.4.10, "Residual Heat Removal (RHR)

Shutdown Cooling SystemCold Shutdown"; LCO 3.9.8, "Residual Heat Removal (RHR)High Water Level"; and LCO 3.9.9, "Residual Heat Removal (RHR)Low Water Level."

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 With one RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced, however, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

(continued)

RHR Shutdown Cooling SystemHot Shutdown B 3.4.9 LaSalle 1 and 2 B 3.4.9-4 Revision 87 BASES ACTIONS A.1 (continued)

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and S/RVs, or an inoperable but functional RHR shutdown cooling subsystem.

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.

C.1, C.2, and C.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as is permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or one 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicable (continued)

E.1, E.2, and E.3 Insert 4

Insert 4 C.1 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and S/RVs, or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

RHR Shutdown Cooling SystemHot Shutdown B 3.4.9 LaSalle 1 and 2 B 3.4.9-5 Revision 87 BASES ACTIONS C.1, C.2, and C.3 (continued) 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.9.1 REQUIREMENTS 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

SR 3.4.9.2 RHR Shutdown Cooling System piping and components have the potential to develop voids and pockets of entrained gases.

Preventing and managing gas intrusion and accumulation is necessary for proper operation of the RHR shutdown cooling subsystems and may also prevent water hammer, pump (continued)

E.1, E.2, and E.3

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.5 Nine Mile Point Nuclear Station, Unit 2 Renewed Facility Operating License No. NPF-69 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4.9-3 B 3.4.9-4

RHR Shutdown Cooling System - Hot Shutdown B 3.4.9 NMP2 B 3.4.9-3 Revision 0, 9 (A109), 63 (A185)

BASES (continued)

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 With one RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the overall reliability is reduced, however, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

(continued)

RHR Shutdown Cooling System - Hot Shutdown B 3.4.9 NMP2 B 3.4.9-4 Revision 0, 63 (A185)

BASES ACTIONS A.1 (continued)

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and S/RVs, or an inoperable but functional RHR shutdown cooling subsystem.

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.

C.1, C.2, and C.3 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as is permitted by LCO Note 1, reactor coolant circulation by the RHR shutdown cooling subsystem or one 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

(continued)

E.1, E.2, and E.3 Insert 5

Insert 5 C.1 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and S/RVs, or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.6 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 REVISED TECHNICAL SPECIFICATIONS BASES PAGES Peach Bottom Atomic Power Station, Unit 2 B 3.4-36 B 3.4-37 Peach Bottom Atomic Power Station, Unit 3 B 3.4-36 B 3.4-37

RHR Shutdown Cooling System Hot Shutdown B 3.4.7 BASES ACTIONS A.1 (continued) overall reliability is reduced, however, 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 required 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Main Steam Systems, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

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.

C.1, C.2 and C.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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicable separately for each occurrence involving a loss of coolant (continued)

PBAPS UNIT 2 B 3.4-36 Revision No. 160 E.1, E.2, and E.3 Insert 6

Insert 6 C.1 With both required 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Main Steam Systems, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

RHR Shutdown Cooling System Hot Shutdown B 3.4.7 BASES ACTIONS C.1, C.2 and C.3 (continued) circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one required 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 setpoint 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

SR 3.4.7.2 RHR Shutdown Cooling (SDC) System piping and components have the potential to develop voids and pockets of entrained gases. Preventing and managing gas intrusion and accumulation is necessary for proper operation of the required RHR shutdown cooling subsystems and may also prevent water hammer, pump cavitation, and pumping of noncondensible gas into the reactor vessel.

(continued)

PBAPS UNIT 2 B 3.4-37 Revision No. 160 E.1, E.2, and E.3

RHR Shutdown Cooling SystemHot Shutdown B 3.4.7 BASES ACTIONS A.1 (continued) overall reliability is reduced, however, 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 required 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Main Steam Systems, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

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.

C.1, C.2, and C.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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the coolant circulation function and is modified such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicable separately for each occurrence involving a loss of coolant (continued)

PBAPS UNIT 3 B 3.4-36 Revision No. 157 E.1, E.2, and E.3 Insert 6

RHR Shutdown Cooling SystemHot Shutdown B 3.4.7 BASES ACTIONS C.1, C.2, and C.3 (continued) circulation. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 periodically monitored to ensure proper function of the alternate method. The once per hour Completion Time is deemed appropriate.

SURVEILLANCE SR 3.4.7.1 REQUIREMENTS This Surveillance verifies that one required 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 setpoint 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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.

SR 3.4.7.2 RHR Shutdown Cooling (SDC) System piping and components have the potential to develop voids and pockets of entrained gases. Preventing and managing gas intrusion and accumulation is necessary for proper operation of the required RHR shutdown cooling subsystems and may also prevent water hammer, pump cavitation, and pumping of noncondensible gas into the reactor vessel.

(continued)

PBAPS UNIT 3 B 3.4-37 Revision No. 157 E.1, E.2, and E.3

ATTACHMENT 4 Markup of Proposed Technical Specifications Bases Pages (Information Only) 4.7 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4.7-3 B 3.4.7-4

RHR Shutdown Cooling SystemHot Shutdown B 3.4.7 Quad Cities 1 and 2 B 3.4.7-3 Revision 72 BASES APPLICABILITY The requirements for decay heat removal in MODES 4 and 5 are (continued) discussed in LCO 3.4.8, "Residual Heat Removal (RHR)

Shutdown Cooling SystemCold Shutdown"; LCO 3.9.8, "Residual Heat Removal (RHR)High Water Level"; and LCO 3.9.9, "Residual Heat Removal (RHR)Low Water Level."

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, and A.3 With one RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by the LCO Note, the overall reliability is reduced 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 (Required Action A.1).

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

(continued)

RHR Shutdown Cooling SystemHot Shutdown B 3.4.7 Quad Cities 1 and 2 B 3.4.7-4 Revision 72 BASES ACTIONS A.1, A.2, and A.3 (continued)

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System in the decay heat removal mode (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and relief valve(s), or an inoperable but functional RHR shutdown cooling subsystem.

In addition, with both RHR shutdown cooling subsystems inoperable, an alternate method of reactor coolant circulation must be placed into service (Required Action A.2). This alternate method may be satisfied by placing a recirculation pump in operation. This will provide the necessary circulation for monitoring coolant temperature.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the importance of the coolant circulation function. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 an RHR shutdown cooling subsystem), the reactor coolant temperature and pressure must be periodically monitored to ensure proper function of the alternate method (Required Action A.3). The once per hour Completion Time is deemed appropriate.

Required Actions A.2 and A.3 are modified by Notes that clarify that these Required Actions are only applicable when both RHR shutdown cooling subsystems are inoperable since Condition A is applicable when one or two RHR shutdown cooling subsystems are inoperable.

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.

(continued)

Insert 7

Insert 7 C.1 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will provide assurance of continued heat removal capability.

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 Condensate/Feed and Main Steam Systems, the Reactor Water Cleanup System in the decay heat removal mode (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), a combination of an ECCS pump and relief valve(s), or an inoperable but functional RHR shutdown cooling subsystem.

D.1 If the required alternate methods of decay heat removal cannot be verified within one hour, immediate action must be taken to restore at least one RHR shutdown cooling subsystem to OPERABLE status. The immediate Completion Time reflects the importance of restoring a method of heat removal.

Required Action D.1 is modified by a Note indicating that all required MODE changes to MODE 4 may be suspended until one RHR shutdown cooling subsystem is restored to OPERABLE status. In this case, LCO 3.0.3 and other Required Actions directing entry into MODE 4 could force the unit into a less safe condition in which there may be no adequate means to remove decay heat. It is more appropriate to allow the restoration of one of the RHR shutdown cooling subsystems before requiring entry into a condition in which that subsystem would be needed and exiting a condition where other sources of cooling are available.

When at least one RHR subsystem is restored to OPERABLE status, the Completion Times of LCO 3.0.3 or other Required Actions resume at the point at which they were suspended.

Insert 7 E.1, E.2, and E.3 With both RHR shutdown cooling subsystems inoperable, an alternate method of reactor coolant circulation must be placed into service. This alternate method may be satisfied by placing a recirculation pump in operation. This will provide the necessary circulation for monitoring coolant temperature. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on the importance of the coolant circulation function. Furthermore, verification of the functioning of the alternate method must be reconfirmed every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 an RHR shutdown cooling subsystem),

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.

v t e Letter Sequence Request
EPID:L-2023-LLA-0077, TSTF-580 (Approved, Closed)
Initiation Request, Request Acceptance Administration Questions 21 September 2023 Answers Results Approval Other:
MONTHYEAR2023-05-25 [Table View]

RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling

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RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling

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