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County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems
	ML20104C104
Person / Time
Site:	Dresden, Peach Bottom, Nine Mile Point, Clinton, Quad Cities, FitzPatrick, LaSalle
Issue date:	04/13/2020
From:	Simpson P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	RS-20-016
	Download: ML20104C104 (100)
	v • d • e

4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 657 2000 Office RS-20-016 April 13, 2020 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 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 10 CFR 50.90

Subject:

Application to Revise Technical Specifications to Adopt TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Systems"

Reference:

Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluations of Technical Specifications Task Force Traveler TSTF-566, Revision 0, 'Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,"' dated February 21, 2019

April 13, 2020 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," Exelon Generation Company, LLC (EGC), 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, 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 566 (TSTF-566), Revision 0, "Revise Actions for Inoperable RHR Shutdown Cooling Systems." provides a description and assessment of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change. Attachment 3 provides TS Bases pages marked up to show the associated TS Bases changes and is provided for information only.

The proposed change has been reviewed by the Plant Operations Review Committees at each station in accordance with the requirements of the EGC Quality Assurance Program.

EGC requests approval of the proposed change by April 13, 2021. 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), EGC 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.

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.

April 13, 2020 U.S. Nuclear Regulatory Commission Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 13th day of April 2020.

Respectfully, P~R '

PatrickR.~

Sr. Manager Licensing Attachments:

1. Description and Assessment

2. Markup of Proposed Technical Specifications Pages

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

NRC Regional Administrator, Region I NRC Regional Administrator, Region Ill 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

1.0 DESCRIPTION

ATTACHMENT 1 Description and Assessment Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 566 (TSTF-566), "Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems," which is an approved change to the Improved Standard Technical Specifications (ISTS), into 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, Technical Specifications (TS). The proposed amendment revises the TS actions applicable when a residual heat removal (RHR) shutdown cooling subsystem is inoperable.

2.0 ASSESSMENT

2.1 Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-566 provided to the Technical Specifications Task Force in a letter dated February 21, 2019 (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-566 (Reference 1 ). As described below, EGC has concluded that the justifications presented in TSTF-566 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 EGC plants TS utilize different numbering than the Standard TS on which TSTF-566 was based (Reference 3 and 4). Additionally, Dresden utilizes a different title and system name designation. The specific differences between the plant TS and TSTF-566 are described in Table 1. These differences are administrative and do not affect the applicability of TSTF-566 to the EGC plants TS.

Page 1

ATTACHMENT 1 Description and Assessment Table 1. Specific Differences Between EGC TS and TSTF-566 (NUREG-1433)

TSTF-566 Dresden FitzPatrick Peach Bottom Quad Cities (NUREG-1433)

Numbering and 3.4.8 Residual title difference Numbering Numbering Numbering Heat Removal (RHR) Shutdown 3.4.7 Shutdown difference difference difference Cooling System -

Cooling (SOC) 3.4.7 3.4.7 3.4.7 Hot Shutdown System-Hot Shutdown Numbering and 3.4.8 Action B.1 system name designation Initiate action to difference restore RHR 3.4.7 Action B.1 None None None shutdown cooling Initiate action to subsystem(s) to restore SOC OPERABLE subsystem(s) to status.

OPERABLE status.

Numbering and 3.4.9 Residual title difference Numbering Numbering Numbering Heat Removal (RHR) Shutdown 3.4.8 Shutdown difference difference difference Cooling System -

Cooling (SOC) 3.4.8 3.4.8 3.4.8 Cold Shutdown System-Cold Shutdown Numbering and system name 3.4.9 Action B.1 designation difference Initiate action to restore RHR 3.4.8 Action B.1 None None None shutdown cooling subsystem(s) to Initiate action to OPERABLE restore SOC status.

subsystem(s) to OPERABLE status.

Note: No differences were identified between NUREG-1434 and plant TS (i.e., Clinton, LaSalle, and Nine Mile Point 2).

Page 2

ATTACHMENT 1 Description and Assessment

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Analysis EGC requests adoption of TSTF-566, "Revise Actions for Inoperable RHR Shutdown Cooling Subsystems," which is an approved change to the ISTS, into the 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, TS.

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

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

1.

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

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

The design and function of the RHR System are not affected by the proposed change.

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

2.

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

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

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

Page 3

ATTACHMENT 1 Description and Assessment

3.

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

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

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

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

3.2 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 CONSIDERATION

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

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

5.0 REFERENCES

1. Letter from the Technical Specifications Task Force to the U.S. Nuclear Regulatory Commission, "Transmittal of TSTF-566, Revision 0, 'Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,"' dated January 19, 2018 Page 4

ATTACHMENT 1 Description and Assessment

2. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluations of Technical Specifications Task Force Traveler TSTF-566, Revision 0,

'Revise Actions for Inoperable RHR Shutdown Cooling Subsystems,"' dated February 21, 2019

3. NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 4, dated April 2012

4. NUREG-1434, Standard Technical Specifications, General Electric BWR/6 Plants, Volume 1, Revision 4, dated April 2012 Page 5

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 3.4-23 3.4-24 3.4-26

ACT I ONS (continued)

CONDIT I ON A.

One or two RHR shutdown coo l ing subsystems inoperabl e.

+..

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

CL I NTON RHR Shutdown Cooling System ~ Hot Shutdown

3. 4. 9 REQUIRED ACTION COMPLETION TIME A-.1.

Ir:dtjatt= actj OD t o Iww~dj at~J ~'

r:12 st or:~ BBB sbJJtdcnein:l coo ] Jug SJJbS¥St""Ill ( S )

to O PEB ABIE stat n s A1ill A...2.

Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

~

method of decay heat removal is available for each inoperable AND RHR shutdown cooling subsystem.

Once per 24 h thereafter A1ill 1L..3.

B""

j D

~ODE a 2'1 bOJJ l: S

~

(continued)

B. 1 Initiate action to restore RHR Shutdown Cooling

~Immediately subsystem(s) to OPERABLE status.

3.4 - 23 Amendment No..9..5.

ours I

RHR Shutdown Cooling System ~ Hot Shutdown

3. 4. 9 ACTIONS (cont i nued )

CONDITION REQUIRED ACTION No RHR shutdown cooling subsystem in operation.

B..-1.. I nitiate action to restore one RHR shutdown coo l ing subsystem or one recircu l ation pump to operation.

AND No recircu l ation pump AND in operation.

B-.2..._Verify reactor coo l ant circul ation by an a l ternate method.

2 AND B.-3. Monitor reactor coo l ant temperature and pressure.

==============iC.3 SURVE I LLANCE REQU I REMENTS SR 3.4.9. 1 CL I NTON SURVEILLANCE

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

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

Verify one RHR shutdown coo l ing subsystem or recircu l ation pump is operating.

3.4 - 2 4 COMPLETION TI ME I mmediate l y 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coo l ant circul ation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour FREQUENCY I n accordance with the Surveillance Frequency Contro l program (continued ).A--

Amendment No..2..011.

RHR Shutdown Cooling System ~ Co l d Shutdown

3. 4. 10 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.

I Immediately I

)

nued )

COND I TION No RHR shutdown coo l ing subsystem i n operati on.

AND No rec i rcu l at i on pump in operati on.

)

I /

REQU I RED ACT I ON AND Veri fy reactor coo l ant circul ating by an a l ternate method.

Mon i tor reactor coo l ant temperature and pressure.

SURVE I LLANCE REQU I REMENTS SR 3.4. 10. 1 SR 3.4. 10.2 CL I NTON SURVEILLANCE Verify one RHR shutdown coo l ing subsystem or recircu l ation pump is operating.

Verify RHR shutdown coo l ing subsystem l ocations susceptibl e to gas accumulation are sufficientl y fi lled with water.

3.4 - 26

)

,f OMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from d i scovery of no reactor coo l ant c i rcu l at i on AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour FREQUENCY I n accordance with the Surveillance Frequency Contro l Program I n accordance with the Surveillance Frequency Contro l Program Amendment No..2..011.

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 3.4.8-1 3.4.8-2

SDC System-Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Shutdown Cooling (SOC) System-Hot Shutdown LCO

3.4.7 APPLICABILITY

ACTIONS Two SDC subsys tems shall be OPERABLE, and, with no recirculation pump in operation, at lea st one SDC subsys tem shall be in operation.

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

1.

Both required SDC subsys tems and recirculation pumps may be not in operation for up to 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2.

One required SDC subsys tem may be inoperable for up to 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s for the performance of Surveillances.

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

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - N 0 TE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Ir Separate Condition entry i s allowed for each SDC subsystem.

,.{

CONDITION A.

One or t wo required SDC subsystems inoperable.

Dresden 2 and 3 REQUIRED ACT ION IAitiate actioA to restore required SOC subsystem(s) to OPERABLE status.

COMPLETION TIME Immediately (con tinued )

3.4.7 -1 Amendmen t No. 212/204

ACTIONS CONDITION A.

(continued)

£-;-

No required SDC subsystem in operation.

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

AND No recirculation in operation.

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

Dresden 2 and 3 SDC System-Hot Shutdown 3.4.7 REQUIRED ACT ION Verify an alternate method of decay heat removal is available for each inoperable required SDC subsystem.

Be iA

~rnDE 4.

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

Verify reactor coolant circulation by an alternate method.

Monitor reactor coolant temperature and pressure.

COMPLETION TIME 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 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s

~

!immediately I 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 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour 3.4.7-2 Amendment No. 185/ 180

SDC System-Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Shutdown Cooling (SOC) System-Cold Shutdown LCO 3.4.8 APP LICABILITY:

ACTIONS Two SDC subsystems sha ll be OPERABLE, and, with no recirculation pump in operation, at lea st one SDC subsystem sha ll be in operation.

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

1.

Both required SDC subsystems may be not in operation during hydrostatic testing.

2.

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.

3.

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.

MODE 4.

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

Separate Condition entry i s allowed for each shutdown coo ling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required A.l Ver ify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SDC subsystems method of decay heat inoperable.

removal i s available AND for each in operable required SDC Once per subsystem.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter I[\\

A'

'I' (cont inued )

B. Required Action B. 1 Initiate action to and associated restore SOC I Immediately I

Completion Time of subsystem(s) to Condition A not met.

OPERABLE status.

Dresden 2 and 3 3.4.8 -1 Amendment No. 185/ 180

SDC System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION

£-;-

No required SDC B-:4-Verify reactor d

subsystem in

~

coolant circulating operation.

by an alternate method.

AND No recirculation pump in operation.

AND

£-: Monitor reactor t

coo lant temperature and pressure.

IC.2 I SURVEILLANCE REQUIREMENTS SR 3.4.8.l SR 3.4.8.2 SURVE ILLANCE Ver ify one SDC subsystem or recirculation pump i s operat ing.

Ver ify SDC subsystem l ocat i ons susceptible to gas accumulation are sufficientl y filled with water.

COMPLETION TIME 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 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Dresden 2 and 3 3.4.8 -2 Amendment No. 244 / 237

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 3.4.8-1

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 APPLICABILITY:

ACTIONS 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.

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

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

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

CONDITION A.

One or two RHR shutdown cooling subsystems inoperable.

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

JAFNPP r

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

REQUIRED ACTION COMPLETION TIME Initiate action to restore Immediately RHR shutdown coaling subsys-tem(s) to OPERABLE status.

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

Be in MODE 4.

3.4.7-1 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pm_ m_e-di-a-te-ly I Amendment 284

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.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - 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:

MODE4.

ACTIONS

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

Separate Condition entry is allowed for each shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystems of decay heat removal is inoperable.

available for each Af!Q inoperable RHR shutdown cooling subsystem.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter

~

?/

ft...

B. Required Action and B. 1 Initiate action to restore RHR l

associated Completion Time shutdown cooling subsystem(s) to I Immediately I

of Condition A not met.

OPERABLE status.

SURVEILLANCE REQUIREMENTS SR 3.4.8.1 JAFNPP SURVEILLANCE Verify each 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.

3.4.S..1 FREQUENCY In accordance with the Surveillance Frequency Control Program Am en dment--361. 4'"

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 3.4.10-2

RHR Shutdown Cooling System-Hot Shutdown 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System-Hot Shutdown LCO

3.4.9 APPLICABILITY

ACTIONS 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.

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

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

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

CONDITION A.

One or two RHR A-:-+

shutdown cooling subsystems inoperable.

LaSalle 1 and 2 REQUIRED ACTION Initiate action to restore RHR shutdown cooling subsystem to OPERABLE status.

COMPLETION TIME Immediately (continued) 3.4.9-1 Amendment No. 171/157

ACTIONS CONDITION A.

(continued)

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

\\ '/

No RHR shutdown cooling subsystem in operation.

No recirculation pump in operation.

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

LaSalle 1 and 2 I'

I RHR Shutdown Cooling System-Hot Shutdown 3.4.9 REQUIRED ACTION Verify an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

Be in ~rnDE 4.

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

Verify reactor coolant circulation by an alternate method.

COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

/

I AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .--~~~~~~---.!

4E--

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

3.4.9 - 2 Amendment No. 147/133

8. 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.

RHR Shutdown Cooling System-Cold Shutdown 3.4.10 Immediately ACTIONS CONDITION

~ No RHR shutdown

~

cooling subsystem operation.

AND No recirculation in operation.

£-:-+

in

~

pump REQUIRED ACTION Verify reactor coolant circulating by an alternate method.

Monitor reactor coolant temperature and pressure.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SR 3.4.10.2 LaSalle 1 and 2 SURVEILLANCE Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

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

3.4.10-2 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program t Amendment No. 214 / 200

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 3.4.10-2

RHR Shutdown Cooling System - Hot Shutdown 3.4.9 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.

N 0 TES----------------------------------------------

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 A.

One or two RHR shutdown cooling subsystems inoperable.

NMP2 REQUIRED ACTION A:4-Initiate action to restore R~R shutdo11rn cooling subsystem to OPE:RABLE: status.

3.4.9-1 COMPLETION TIME Immediately (continued)

Amendment 91, 109

ACTIONS CONDITION A.

(continued)

~

ANQ

~

-11

/

g,.

No RHR shutdown k

~

cooling subsystem in

~

operation.

AND No recirculation pum in operation.

AND

~

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.

AND

~

1ct1 NMP2 RHR Shutdown Cooling System - Hot Shutdown 3.4.9 REQUIRED ACTION COMPLETION TIME Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat

~

AND removal is available Once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for each inoperable thereafter RHR shutdown cooling subsystem.

Be in MODE 4.

~4 RSl:lFS

~ Immediately I Initiate action to Immediately restore one RHR shutdown cooling subsystem or one recirculation pump to operation.

Verify reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from coolant circulation discovery of no by an alternate reactor coolant method.

circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Monitor reactor Once per hour coolant temperature and pressure.

3.4.9-2 Amendment s+

s

RHR Shutdown Cooling System - Cold Shutdown B. 1 Initiate action to restore RHR shutdown cooling subsystem(s) to ACTIONS (con OPERABLE status.

CONDITION No RHR shutdown cooling subsystem in operation.

No recirculation pump in operation.

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

'/

REQUIRED ACTION Verify reactor coolant circulating by an alternate method.

Monitor reactor coolant temperature and pressure.

SURVEILLANCE REQUIREMENTS SR 3.4.10.1 SR 3.4.10.2 NMP2 SURVEILLANCE Verify one RHR shutdown cooling subsystem or recirculation pump is operating.

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

3.4.10-2 3.4.10

!Immediately I COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of no reactor coolant circulation Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour FREQUENCY In accordance with t the Surveillance Frequency Control Program In accordance with t the Surveillance Frequency Control Program Amendment 91, 150, 152

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 3.4-19 3.4-20 Peach Bottom Atomic Power Station. Unit 3 3.4-16 3.4-17 3.4-19 3.4-20

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 APPLICABILITY

ACTIONS 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.

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

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

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

CONDITION A.

One or two required RHR shutdown cooling subsystems inoperable.

PBAPS UN IT 2 REQUIRED ACTION IAitiate actioA to restore required RHR shutdowA cooliAg subsystem( s) to OPERABLE status.

3.4-16 COMPLETION TIME Immediately (continued)

Amendment No. 5 ACTI ONS COND IT ION A. (cont i nued)

B-:-

No RHR shutdown cooli ng subsystem

~

operat i on.

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

AND No i n B.1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

rec i rcu l at i on operat i on.

PBAPS UN IT 2 i n AND : ~

AND B-:-3

~

RHR Shutdown Cooli ng Sys t em -Hot Shut down 3.4. 7 REQUIR ED ACTI ON Ver i fy an al ternate method of decay heat remova l i s ava il ab l e for each requ i red i noperab l e RHR shutdown coo l ing subsystem.

Be i n MO DE 4.

Ini t i ate act i on to restore one RHR shutdown cooli ng subsystem or one rec i rcu l at i on pump to operat i on.

Ver i fy reactor coo l ant ci rcu l at i on by an al ternate method.

Mon i tor reactor coo l ant temperature and pressure.

3.4-17 COMP LETION TI ME 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

~~lm

~m-e-d-ia_t_

e-ly~~~~

Immed i ate ly 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from di scovery of no reactor coo l ant ci rcu l at i on AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour Amendment No. +/--B-

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 APPLICABILITY

ACTIONS 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.

MODE 4.

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

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

CONDITION REQUIRED ACTION 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.

(

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

PBAPS UN IT 2 B. 1 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

3.4-19 I Immediately COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

I Amendment No. Ht

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

CONDITION REQUIRED ACTION

£-;-

No RHR shutdown

-&-;-}

Verify reactor b cooling subsystem in coolant circulating operation.

~

by an alternate method.

AND No recirculation pump in operation.

AND

£-ti-Monitor reactor

~

coolant temperature and pressure.

SURVEILLANCE REQUIREMENTS SR 3.4.8.1 SR 3.4.8.2 PBAPS UN IT 2 SURVEILLANCE Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

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

HPSW system related components are excluded.

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

3.4-20 COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from disco very 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 FREQUENCY In accordance with the Sur veillance Frequency Control Program.

In accordance with the Surveillance Frequency Control Program.

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 APPLICABILITY

ACTIONS 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.

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

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

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

CONDITION A.

One or two required A-:-+/-

RHR shutdown cooling subsystems inoperable.

PBAPS UN IT 3 REQUIRED ACTION IAitiate actioA to restore required RHR shutdowA cooliAg subsystem( s) to OPERABLE status.

3.4-16 COMPLETION TIME Immediately (continued)

Amendment No. ~

ACTIONS CONDITION A.

(con tinued ) :-

No RHR shutdown b

cooling subsystem in operation.

AND No recirculation ump in operation.

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.

PBAPS UN IT 3 MW

~

B-: ~

AND B-: ~

AND :-3

~

RHR Shutdown Cooling System-Hot Shutdown 3.4.7 REQUIRED ACTION Verify an alternate method of decay heat removal i s available for each required inoperable RHR shutdown coo ling subsystem.

Be i n MODE 4.

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

Verify reactor coolant circulation by an alternate method.

Monitor reactor coolant temperature and pressure.

3.4-17 COMPLETION TIME 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months k-ilmmediately Immediatel y 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 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 APPLICABILITY

ACTIONS 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.

MODE 4.

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

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

CONDITION A.

One or two required A.1 RHR shutdown cooling subsystems inoperable.

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

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

(continued)

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.

I Immediately I

PBAPS UN IT 3 3.4-19 Amendment No. -2+4

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

CONDITION REQUIRED ACTION

£-;-

No RHR shutdown

£..;-}

Verify reactor b

cooling subsystem in

~

coolant circulating operation.

by an alternate method.

AND No recirculation pump in operation.

AND : Monitor reactor

/I\\

coolant temperature and pressure.

fC21 SURVEILLANCE REQUIREMENTS SR 3.4.8.1 SR 3.4.8.2 PBAPS UN IT 3 SURVEILLANCE Verify one required RHR shutdown cooling subsystem or recirculation pump is operating.

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

HPSW system related components are excluded.

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

3.4-20 COMPLETION TIME 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 FREQUENCY In accordance with the Surveillance Frequency Control Program.

In accordance with the Surveillance Frequency Control Program.

Amendment No. -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 3.4.8-2

3.4 REACTOR COO LANT SYSTEM (RCS)

RHR Shutdown Cooli ng System-Hot Shutdown 3.4. 7 3.4. 7 Residual Heat Removal (RHR ) Shutdown Cooling System-Hot Shutdown LCO 3.4. 7 APP LIC AB ILITY:

ACTION S Two RHR shutdown cooli ng 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 Surve illances.

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

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two RHR A-:-+

shutdown cool ing subsystems inoperable.

Quad Cities 1 and 2 Initiate action to restore RHR shutdown cooling subsystem(s) to OPERABLE status.

Immediately (con tinued )

3.4.7 -1 Amendmen t No. 223 / 218

ACTIONS CONDITION A.

(continued)

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

Quad Cities 1 and 2 RHR Shutdown Cooling System-Hot Shutdown 3.4.7 I

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

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

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Verify reactor coolant circulation by an alternate method.

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

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Monitor reactor coolant temperature and pressure.

Be in MODE 4.

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

COMPLETION TIME 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

!Immediately I 3.4.7 -2 Amendment No. 199/195

RHR Shutdown Cooling System-Cold Shutdown 3.4.8 ACTIONS CONDITION REQUIRED ACTION A.

(continued)

A.2

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

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Verify reactor coolant circulating by an alternate method.

A.3

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

Only applicable if both RHR shutdown cooling subsystems are inoperable.

Monitor reactor coolant temperature and pressure.

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.

SURVEILLANCE REQUIREMENTS SR 3.4.8.1 SURVEILLANCE Verify each RHR shutdown cooling subsystem manual and power operated 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.

COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Once per hour l

Immediately I

FREQUENCY In accordance with the Surveillance Frequency Control Program (continued) ~

Quad Cities 1 and 2 3.4.8-2 Amendment No. 257 / 252

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.1 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 REVISED TECHNICAL SPECIFICATIONS BASES PAGES B 3.4-45 B 3.4-46 B 3.4-47 B 3.4-51 B 3.9-27 B 3.9-31

BASES APPL I CABIL I TY (continued )

ACT I ONS CL I NTON RHR Shutdown Cooling System-Hot Shutdown B 3.4.9 The requirements for decay heat removal in MODES 4 and 5 are discussed in LCO 3.4. 10, "Residua l Heat Remova l (RHR )

Shutdown Coo l ing System-Cold Shutdown"; LCO 3. 9. 8,

"Residua l Heat Remova l (RHR)- High Water Level "; and LCO 3. 9. 9, "Res i dua l Heat Remova l (RHR ) -

Low Water Level. "

A Note has been provided to modify the ACT I ONS re l ated to

_.r.-

RHR shutdown coo l ing 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 inoperabl e or not within l imits, will not result in separate entry into the Condition.

Section 1.3 a l so specifies Required Actions of the Condition continue to apply for each additional fai l ure, with Compl etion Times based on initial entry into the Condition.

However, the Required Actions for inoperable shutdown coo l ing subsystems provide appropriate compensatory measures for separate inoperabl e s hutdown cooling subsystems.

As such, a Note has been provided that allows separate Condition entry for each inoperabl e RHR shutdown coo l ing subsystem.

A. l, A 2, a nd A 3 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2,

the i nope r a b l e s 11hs'j'stem m11 st h e r est ored t o OPEB ABTE stat 11 s Jadt h o n t de l a¥ I n t h i s c o nd i t i o n,

t h e r e ma i n i ng OpEB ABTE snh sj'stem c a n p r a*ui de t h e ne c essa r y decay h eat r e mov a l Th e overall re l iabi l ity is reduced, h rn°re v e r, because a single fai l ure in the OPERABLE subsystem could result in reduced RHR shutdown coo l ing capabi l ity.

Therefore an a l ternate method of decay heat remova l must be provided.

(continued )

B 3.4 -4 5 Revision No..l..0.=-3.

BASES ACTIONS 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.

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.

CL I NTON RHR Shutdown Cooling System ~ Hot Shutdown B 3.4.9 A. l,

A 2,

a n d A

3 (continued)

With both RHR shutdown coo l ing subsystems inoperable, an a l ternate method of decay heat removal must be provided in addition to that provided for the initial RHR s hutdown coo l ing subsystem inoperabi l ity.

This re - establ ishes backup decay heat remova l capabi l ities, 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 Compl etion Ti me i s based on t he decay heat remova l funct i on and the probability of a l oss of the avai l abl e decay heat remova l capabilities.

~~~~~~~~~~~~:r~~~~~::~~~~Jsufficient The be i ts c apa b ili ty to ma i nta i n or reduce temperature at or below 200°F.

Decay heat removal by ambient l osses can be cons i dered as, or contributing to, the alternate method capabi l ity.

Al ternate methods that can be used include (but are not l imited to ) the Reactor Water Cl eanup System_

B J '

B 2 '

a n d B

3 ~<-----ilc.1. C.2, and C.3

, or an inoperable but functional RHR shutdown cooling subsystem.

With no RHR shutdown coo l ing subsystem and no recirculation pump in operation, except as is permitted by LCO Note 1,

reactor coo l ant circul at i on by the RHR shutdown cooling subsystem or one rec i rcu l ation pump must be restored without de l ay.

Unti l RHR or rec i rcu l ation pump operation is re - establ ished, an a l ternate method of reactor coolant circulation must be p l aced into servi ce.

Thi s will provide t he necessary circul at i on for monitoring coo l ant temperature.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Compl etion Ti me i s based on the coolant circul at i on function and i s modifi ed such that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is applicabl e separatel y for each occurrence involving a loss of coolant circul at i on.

Furthermore, verification of the functioning of the a l ternate 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)

B 3.4 -4 6 Revision No.....l.=..l.

BASES ACTIONS SURVE I LLANCE REQU I REMENTS CL I NTON t

C.1, C.2, and C.3 B

1 '

B 2,

a nd B 3

RHR Shutdown Cooling System ~ Hot Shutdown B 3.4.9 (continued)

During the period when the reactor coolant is being circul ated by an a l ternate method (other t han by t he required RHR shutdown coo l ing subsystem or recirculation pump ), the reactor coo l ant temperature and pressure must be periodicall y monitored to ensure proper function of the a l ternate method.

The once per hour Completion Time is deemed appropriate.

SR 3.4.9. 1 This Surveillance verifies that one RHR s hutdown cooling subsystem or recircu l ation pump is in operation and circul ating reactor coo l ant.

The required flow rate is determined by the f l ow rate necessary to provide sufficient decay heat remova l capabi l ity.

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

This Surveillance is modified by a Note allowing sufficient time to a l ign the RHR System for s hutdown cooling operation after c l earing the pressure interl ock that iso l ates t he system, or for p l acing a recirculation pump in operation.

The Note takes exception to the requirements of t he 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 a l so allows entry into the Appl icabi l ity of this Specification in accordance with SR 3.0. 4 since the Surveillance wi l l not be "not met " at the time of entry into t he Applicability.

SR 3.4.9.2 RHR Shutdown Coo l ing System piping and components have the potential to deve l op voids and pockets of entrained gases.

Preventing and managing gas intrusion and accumulation is necessary for proper operation of t he RHR s hutdown cooling subsystems and may a l so prevent water hammer, pump cavitation, and pumping of noncondensibl e gas into the reactor vesse l.

Sel ection of RHR Shutdown Coo l ing System locations susceptibl e to gas accumu l ation is based on a review of system design information, inc l uding piping and instrumentation drawings, isometric drawings, p l an and e l evation drawings, and ca l cu l ations.

The design review is suppl emented by system wa l k downs to validate t he system high points and to confirm the l ocation and orientation of important components that can become sources of gas or could otherwise cause gas to be trapped or difficult to remove (continued)

B 3.4 -4 7 Revision No..l.1..=..l.

BASES ACTIONS sufficient 8.1 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 and C.2 SURVEILLANCE REQUIREMENTS CLINTON A. l (continued)

RHR Shutdown Cooling System ~ Cold Shutdown B 3.4.10 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.

e required cooling capacity of the alternate method should b

ens nred b ¥ *ue r i f j/ i ng (h j/ c a l cnl at i on o r demonst r at i on )

i t s c apa h i l it¥ to maintain or reduce temperature at or below V 200°F.

Decay heat removal by ambient losses can be

/I considered as, or contributing to, the alternate method capability.

Alternate methods that can be used include (but are not limited to) the Reactor Water Cleanup S ste

,+-

B 2

, or an inoperable but functional RHR

~h11trlnwn r.nnlinn ~11h~v~tP.m RHR shutdown cooling subsystem and no recirculation ump in operation, except as is permitted by LCO Note 1, and ntil RHR or recirculation pump operation is re - established, n alternate method of reactor coolant circulation must be laced 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 circu-lated by an alternate method (other than by the required RHR Shutdown Cooling System 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.

SR 3.4.10.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.

The required flow rate is determined by the flow rate necessary to provide sufficient (continued)

B 3.4 - 51 Revision No..l=1.

BASES ACTIONS The required cooling capacity of the alternate method should be sufficient to maintain or reduce temperature. Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability.

Alternate methods that can be used include (but are not limited to) the Spent Fuel Pool Cooling System, the Reactor Water Cleanup System, or an inoperable but functional RHR shutdown cooling subsystem.

CL I NTON A. l (continued )

Al ternate RHR ~ High Water Leve l B 3.9.8 remova l methods are available to t he and prepl anning in the unit ' s regene rat i 3re heat Spent Fn e l Poo l Coo li ng System the decay heat shou l d be the most prudent choice based on unit conditions.

B. l, B.2, B.3, B.4, and B.5 I f no RHR shutdown coo l ing subsystem is OPERABLE and an a l ternate method of decay heat removal is not available in accordance with Required Action A. l, actions shall be taken immediatel y to suspend operations involving an increase in reactor decay heat l oad by suspending t he loading of irradiated fue l assembl ies into the RPV.

Additiona l actions are required to minimize any potential fission product re l ease to the environment.

This includes ensuring secondary containment is OPERABLE ; one standby gas treatment subsystem is OPERABLE ; and secondary containment iso l ation capabi l ity (i.e., at l east one isolation valve and associated instrumentation are OPERABLE or other acceptable administrative contro l s to assure isolation capability ) in each secondary containment and secondary containment bypass penetration f l ow path not iso l ated that is assumed to be iso l ated to mitigate radioactivity releases.

This may be performed as an administrative check, by examining logs or other information, to determine if the components are out of service for maintenance or other reasons.

I t is not necessary to perform the Survei l lances needed to demonstrate the OPERAB I LI TY of the components.

If, however, any required component is inoperabl e, t hen it must be restored to OPERABLE status.

I n this case, the Surveillances may need to be performed to restore t he component to OPERABLE status.

I n addition, at l east one door in the upper containment personne l air l ock must be closed.

The closed air l ock door compl etes the boundary for control of potential radioactive re l eases.

With the appropriate administrative contro l s however, t he closed door can be opened intermittentl y for entry and exit.

This allowance is acceptabl e due to the need for containment access and due to the s l ow progression of events which may result from inadequate decay heat remova l.

Loss of decay heat removal (continued )

B 3.9 - 27 Revision No..l.=..l.

BASES ACTIONS 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.

CL I NTON A. l (conti nued )

RHR ~ Low Water Leve l B 3.9.9 decay heat remova l must be provi ded.

Wi th both RHR shutdown cooling subsystems i noperabl e, an alternate method of decay heat remova l must be provided in addition to t hat provided for the i nit i a l RHR shutdown cooling subsystem i noperability.

This re - establ ishes backup decay heat remova l capabilities, s i mi l ar to the requirements of t he LCO.

The l hour Compl etion Time is based on t he decay heat remova l function and the probability of a loss of t he avai l abl e decay heat remova l capabilities.

Furthermore,

verification of the functiona l availabi l ity of these a l ternate 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 ensure continued heat removal capability.

nate decay heat remova l methods are available to t he operat for review and prepl anning in t he unit ' s Operating Procedures For e x a mp l e, t h i s ma;r i n c l n de t h e n se of t h e Rea c to r Wate r Cl ea nnp Sj'stem, ope r at i ng wi t h t he r egen e r at i v e heat e x c h a nge r h j'passed The method used to remove decay heat shou l d be the most prudent choice based on unit conditions.

B. l, B.2, B.3, and B.4 With the required RHR shutdown cooling subsystem (s )

inoperabl e and the required a l ternate method (s ) of decay heat remova l not avai l abl e in accordance with Required Action A. l, additiona l actions are required to minimize any potential fission product re l ease to the environment.

This inc l udes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment iso l ation capabi l ity (i. e., at least one iso l ation va l ve and associated instrumentation are OPERABLE or other acceptabl e administrative controls to assure iso l ation capabi l ity ) in each secondary containment and secondary containment bypass penetration flow path not iso l ated that is assumed to be isolated to mitigate radioactivity re l eases.

This may be performed as an administrative check, by examining logs or other information, to determine if the components are out of service for maintenance or other reasons.

It is not necessary to perform the Survei l lances needed to demonstrate the OPERAB I LI TY of the components.

I f, however, any (continued)

B 3. 9-31 Revision No......O.

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.2 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 B 3.4.8-4 B 3.9.8-3 B 3.9.9-3

BASES APPLICABILITY (continued)

ACTIONS Dresden 2 and 3 SDC System-Hot Shutdown B 3.4.7 The requirements for decay heat removal in MODES 4 and 5 are discussed in LCO 3.4.8, "Shutdown Cooling (SOC) System-Cold Shutdown"; LCO 3.9.8, "Shutdown Cooling (SDC)-High Water Level"; and LCO 3.9.9, "Shutdown Cooling (SDC)-Low Water Level."

A Note has been provided to modify the ACTIONS related to If" 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.l. A.2. aAd A.3 With one required SDC subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the iAoperable subsystem must be restored to OPERABLE status without delay.

IA this COAditioA, the remaiAiAg OPERABLE subsystem caA provide the Aecessary decay heat removal.

i:fT. overall reliability is reduced, however, 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.

(continued)

B 3.4.7-3 Revision ti

B.1 BASES ACTIONS 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.

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 SOC 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.

Dresden 2 and 3 A.1. A.2. and A.3 (continued)

SDC System-Hot Shutdown B 3.4.7 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.

Thi s 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 i s based on the decay heat removal function and the probability of a loss of the available decay heat capability to maintain or reduce temperature.

Decay heat removal by ambient losse s 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, itt't4 the Reactor Water Cleanup System (by it self or using feed and bleed in combination with the Control Rod Drive System or

..---~~~~~~~~~~~~~~~---.

Condensate/Feed System).

, or an inoperable but functional SOC subsystem.

MODE 4 i s en t ered.

B. 1. B. 2. and B. 3 +-(-----1IC.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.

Thi s 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 i s based on the coolant circulation function and i s 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 in volv ing a loss of coolant circulation.

Furthermore, ver ification 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.

(con tinued )

B 3.4.7-4 Revision B

BASES ACTIONS SURVEILLANCE REQUIREMENTS Dresden 2 and 3 r

C.1, C.2, and C.3 8.1. 8.2. an d 8.3 (continued)

SDC System-Hot Shutdown B 3.4.7 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 coo lant temperature and pressure must be periodically monitored to ensure proper function of the alternate method.

The once per hour Completion Time is deemed appropriate.

SR 3.4.7.1 Thi s Surveillance ver ifies that one SDC subsystem or recirculation pump i s 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 Frequen cy i s controlled under the Surveillance Frequency Control Program.

Thi s Surveillance i s 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 i s not required for this initial 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period), wh ich 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 vo id s 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, i sometr ic drawings, plan and elevation drawings, and calculations.

The design review is supplemented by system (con tinued )

B 3.4.7-5 Revision M

BASES ACTIONS sufficient 8.1 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 SOC 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.

Dresden 2 and 3 A......l (continued)

SDC System-Cold Shutdown B 3.4.8 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.

capab ili ty 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 System -a-A-4 the Reactor Water Cleanup System (by itself or using ' feed and bleed in combination with the Control Rod Drive System or Condensate IF e ed System l-:-

, or an inoperable but functional SOC subsystem.

~~~

B.~2

~<----1IC.1 and C.2 I With no required SDC subsystem and no recirculation pump in operation, except as permitted by LCO Notes 1 and 2, and 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.

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

B 3.4.8-4 Revision B

BASES ACTIONS Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Spent Fuel Pool Cooling System, the Reactor Water Cleanup System Dresden 2 and 3 sufficient A......l (continued)

SOC-High Water Level B 3.9.8 verification of he functional availability of the alternate method must be r confirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

Thi s will ensure cont nued heat removal capability.

Alternate decay eat removal methods are available to the operators for re iew and preplanning in the unit operating procedures.

The equired cooling capacity of the alternate method shou ld be eAsured by verifyiAg (by calculatioA or demoAstratioA) its capability to maintain or reduce tern era For example, this may iAclude the use of the Fuel Pool CooliAg or Reactor Water CleaAup System operatiAg with the regeAerative heat exchaAger bypassed or in combination with the Control Rod Drive System or Condensate/

Feed System The method used to remove the decay heat shou ld be the most prudent choice based on unit conditions.

or an inoperable but functional SOC subsystem.

B.l. B.2. B.3. and B.4 If no shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Act i on A.l, actions sha ll be taken immediatel y to suspend operat i ons involving an increase in reactor decay heat l oad by suspending loading of irradiated fuel assemblies into the RPV.

Additional actions are required to m1n1m1ze any potential fission product release to the environment.

Thi s includes ensuring secondary containment i s OPERABLE; one standby gas treatment subsystem i s OPERABLE; and secondary conta inment i solati on capability i s available in each associated penetration flow path not i so lated that i s assumed to be i so lated to mitigate radioactive releases (i.e., one secondary containment i solati on valve and associated in strumentat i on are OPERABLE or other acceptable administrative controls to assure isolation capability.

The se administrative controls consist of station ing a dedicated operator, who i s in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly i solated when a need for secondary containment i so lation is indi cated).

Thi s may be performed as an administrative check, by (cont inued )

B 3.9.8 -3 Revision B

BASES ACTIONS Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability. Alternate methods that can be used include (but are not limited to) the Spent Fuel Pool Cooling System, the Reactor Water Cleanup System

, or an inoperable but functional SOC subsystem.

Dresden 2 and 3 sufficient A......l (continued)

SDC-Low Water Level B 3.9.9 Alternate decay eat removal methods are available to the operators for re procedures.

The method should be *.....,_...-..+........._'++-.......,._.,.................................... __..,......,..._....,.................. ---+-H,..._+++'-

in with the Control Rod Drive System or Condensate/

The method used to remove decay heat should be udent choice based on unit conditions.

A is modified by a Note allowing separate on entry for each inoperable SDC subsystem.

This is acce table since the Required Actions for this Condition pro ide appropriate compensatory actions for each inoperable S

subsystem.

Complying with the Required Actions allow or continued operation.

A subsequent inoperable subsystem is governed by subsequent entry into the Condition and application of the Required Actions B.l. B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.

These administrative controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly isolated when a (continued)

B 3.9.9-3 Revision B

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.3 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 B 3.4.8-3 B 3.4.8-4 B 3.9.7-2 B 3.9.8-2 B 3.9.8-3

BASES APPLICABILITY (continued)

ACTIONS JAFNPP RHR Shutdown Cooling System - Hot Shutdown B 3.4.7 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.*

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 required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by the LCO Note, the iAepeFaele s1:Jesystem m1:Jst ee Festered te OPERABLE status without delay. IA this eenditien, the remaining OPERABLE subsysten 1 car 1 previde the neeessary deeay heat remo<tal. 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 (continued)

B 3.4.7-3 Revision-i2

BASES ACTIONS 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.

B.1 SURVEILLANCE REQUIREMENTS 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.

JAFNPP RHR Shutdown Cooling System - Hot Shutdown 8 3.4.7 A.1. A.2. and A.3 (continued) 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'l' The required cooling capacity of the alternate method should be ensured by verifying (by ealeutation or demonstration) its capability 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 sufficient Condensate System), er-a combination of an RHR pump and safety/relief valve(s).~. or an inoperable but functional RHR shutdown cooling subsystem.

Howe*1er, due to the f)etentially reduced reliability of the alterriate methods of deeay heat remeval, it is also reeiuired to reduee the reactor eoolarit temperature to the poirtt where MODE 4 is entered.

j "\\

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 f,'alves 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.

(continued) 8 3.4.7-4 Revision ae-1

BASES APPLICABILITY (continued)

ACTIONS RHR Shutdown Cool i ng System - Cold Shutdown B 3.4.8 System-Hot Shutdown"; LCO 3.9.7. "Residual Heat Removal (RHR)-High Water Level"; and LCO 3.9.8, "Residual Heat Removal <RHR) - Low Water Level. "

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.l With one of the two required RHR shutdown cooling subsystems inoperable. except as permitted by the LCO Note. the remaining subsystem is capable of providing the required decay heat removal.

However. the overall reliability is reduced. 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.

lsufficient l 1---... "-:(he required cooling capacity of the alternate method should b~ eflst:Jred by verifyiflg (by ealeulation or demonstration ~

its ca~ability 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)

(continued)

JAFNPP B 3.4.8-3 Revision -6

B.1 BASES ACTIONS SURVEILLANCE REQUIREMENTS REFERENCES A.1 (continued)

RHR Shutdown Cooling System - Cold Shutdown 8 3.4.8 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), 6f a combination of an RHR pump and

,safety/relief valve(s).°"

I, or an inoperable but functional RHR shutdown I

.....---,,~

cooling subsystem.

SR 3.4.8.1 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.

1. UFSAR, Chapter 14.

2. 10 CFR 50.36(C)(2)(ii).

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.

JAFNPP 63.4.~4 Revision-8e I

BASES LCO (continued)

APPLICABILITY ACTIONS RHR - High Water Level B 3.9.7 Additionally, each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (from the control room or locally) in the shutdown cooling mode for removal of decay heat. Operation (either continuous or intermittent) of one subsystem can maintain and reduce the reactor coolant temperature as required.

One RHR shutdown cooling subsystem must be OPERABLE in MODE 5. with irradiated fuel in the reactor pressure vessel and with the water level

~ 22 ft 2 inches above the top of the RPV flange, to provide decay heat removal.

RHR shutdown cooling subsystem requirements in other MODES are covered by LCOs in Section 3.4. Reactor Coolant System (RCS).

RHR shutdown cooling subsystem requirements in MODE 5 with irradiated fuel in the reactor pressure vessel and with the water level < 22 ft 2 inches above the top of the RPV flange are given in LCD 3.9.8, "Residual Heat Removal CRHR)-Low Water Level".

A.1 With no RHR shutdown cooling subsystem OPERABLE. an alternate method of decay heat removal must be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In this condition, the volume of water above the top of the RPV flange provides adequate capability to remove decay heat from the reactor core.

However. the overall reliability is reduced because loss of water level could result in reduced decay heat removal capability. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on decay heat removal function and the probability of a loss of the available decay heat removal capabilities. Furthermore. verification of the functional availability of the alternate method must be reconfirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will ensure continued heat removal capability.

!sufficient I Alternate decay heat removal methods are available to the operator~ for rey ~ew and preplanning in the plant Operating Procedures.

Th~equired cooling capacity of the alternate method should be e11sured by ve1ifyi119 (by cal cul atio11 01 demonstration) its capability to maintain or reduce temperatur For example, this may i11clude the use of the Alternate methods that can be used include (but are not limited to)

JAFNPP Spen ool Cooling Syste111 and the Reactor Water Cleanup s em. ope1 ati ng with the rege1ie1 ati ve heat excl 1a11ge1 bypassed or in combination with the Control Rod Drive System or Condensate Syste In addition. the Decay Heat Removal

, or an inoperable but functional RHR shutdown cooling subsystem B 3.9.7*2 (continued)

Revision 6-

BASES LCO (continued)

APPLICABILITY ACTIONS sufficient Alternate methods that can be used include (but are not limited to)

JAFNPP RHR - Low Water Leve 1 B 3.9.8 removal of decay heat. Operation (either continuous or intermittent) of one subsystem can maintain and reduce the reactor coolant temperature as required.

Two RHR shutdown cooling subsystems are required to be OPERABLE in MOOE 5, with irradiated fuel in the RPV and with the water level < 22 ft 2 inches above the top of the RPV flange, to provide decay heat removal.

RHR shutdown cooling subsystem requirements in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS).

RHR shutdown cooling subsystem requirements in MODE 5 with irradiated fuel in the RPV and with the water level

~ 22 ft 2 inches above the top of the RPV flange are given in LCO 3.9.7, "Residual Heat Removal <RHR) -High Water Level."

A.l With one of the two required RHR shutdown cooling subsystems inoperable. the remaining subsystem is capable of providing the required decay heat removal.

However, the overall reliability is reduced. 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 this alternate method must be reconfirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter. This will ensure continued heat removal capability.

Alt ate decay heat removal methods are available to the operato for review and preplanning in the plant Operating Procedures.

required cooling capacity of the alternate method should b ensured by verifying (by calculatio11 01 demonst1 ation) its capacity to maintain or reduce empera

. For example, this may i 11cl ude tl1e use of the Spent Fuel Pool Cooling System>tmd-the Reactor Water Cleanup System, ope1 ating with tl1e 1 egenerati ve lieat excl1a11ge1 bypassed 01 in combination with the Control Rod Drive System (continued)

B 3.9.8-2 Revision e-

BASES ACTIONS SURVEILLANCE REQUIREMENTS JAFNPP

, or an inoperable but functional RHR shutdown cooling subsystem.

A.l (continued)

RHR - Low Water Level B 3.9.8 or Condensate Syste The method used to remove decay heat should be the most prudent choice based on plant conditions.

Decay heat removal by ambient losses can be considered as, or contributing to, the alternate method capability.

B.l, B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE: one standby gas treatment subsystem is OPERABLE: and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e.. one secondary containment isolation valve and associated instrumentation are OPERABLE or acceptable administrative controls assure isolation capability. These administrative controls consist of stationing an operator, who is in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly isolated when a need for secondary containment is indicated). This may be performed as an administrative check. by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.

It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it must be restored to OPERABLE status.

In this case. the surveillance may need to be performed to restore the component to OPERABLE status.

Actions must continue until all required components are OPERABLE.

SR 3.9.8.1 Verifying the correct alignment for manual, power operated.

and automatic valves in the RHR shutdown cooling flow paths 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 (continued)

B 3.9.8-3 Revision ~

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.4 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 B 3.4.10-4 B 3.4.10-5 B 3.9.8-3 B 3.9.9-3

BASES APPLICABILITY (continued)

LaSalle 1 and 2 RHR Shutdown Cooling System-Hot Shutdown B 3.4.9 The requirements for decay heat removal in MODES 4 and 5 are discussed in LCO 3.4.10, "Residual Heat Removal (RHR)

Shutdown Cooling System-Cold 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 Ii' 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 aAd A. 3 With one RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the iAoperable subsystem must be restored to OPERABLE status without delay.

IA this COAditioA, the remaiAiAg OPERABLE subsystem caA provide the Aecessary decay heat removal.

i:fl.e 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.

(continued)

B 3.4.9-3 Revision +9-

BASES ACTIONS 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.

sufficient 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.

LaSalle 1 and 2 RHR Shutdown Cooling System-Hot Shutdown B 3.4.9 A.1. A.2. and A.3 (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 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 remova he probability of a loss of the available decay heat removal capab1 i

required cooling capacity of the alternate method should ensured by ver i fy i ng (by calculation or demonstrat i on) 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 B-r-the Reactor Water Cleanup System (by itself or using feed and bleed in combination with the Control Rod Drive System or Condensate/Feed System), il-l'T4 a combination of an ECCS pump and S/RVs-

, or an inoperable but functional RHR shutdown cooling subsystem.

" :tJ.P-',J-P-'1"---i=l+f-it::++1;=+=1'++:<=i:+;:;+:!'G'+!=l=;::i=!=!=l7==!'!+:i+'l+t+=l='+'l==!'!'P++:;:i+;+i=++:!i7=<~=i=l:;+s:""~~

to reduce MODE 4 is entered.

/

8.1. 8.2. and 8.3 tjc.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)

B 3.4.9-4 Revision.Q.

BASES ACTIONS SURVEILLANCE REQUIREMENTS LaSalle 1 and 2 t

C.1, C.2, and C.3 RHR Shutdown Cooling System-Hot Shutdown B 3.4.9

8. 1. 8. 2. and 8. 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.

SR 3.4.9.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.

The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability.

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

This Surveillance is modified by a Note allowing sufficient time to align the RHR System for shutdown cooling operation after clearing the pressure interlock that isolates the system, or for placing a recirculation pump in operation.

The Note takes exception to the requirements of the Surveillance being met (i.e., forced coolant circulation is not required for this initial 2 hour2.314815e-5 days 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 p1p1ng 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)

B 3.4.9-5 Revision w

BASES ACTIONS sufficient 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.

LaSalle 1 and 2 A......l (continued)

RHR Shutdown Cooling System-Cold Shutdown B 3.4.10 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.

required cooling capacity of the alternate method should eAsured by verifyiAg (by ca l culatioA or demoAstratioA) i ts capab ili ty 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) iHTEl-a combination of an ECCS pump and S/RVs-:-

~ ~

~~---_J ' or an inoperable but functional RHR shutdown cooling subsystem.

8.1 aAd 8.2 tjc.1 and C.2 I With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as is permitted by LCO Notes 1 and 2, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service.

This will provide the necessary circulation for monitoring coolant temperature.

The 1 hour1.157407e-5 days 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)

B 3.4.10-4 Revision B

BASES ACTIONS SURVEILLANCE REQUIREMENTS LaSalle 1 and 2 RHR Shutdown Cooling System-Cold Shutdown B 3.4.10 r C.1 and C.2 I

8. 1 and 8. 2 (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.

SR 3.4.10.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.

The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability.

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

SR 3.4.10.2 RHR Shutdown Cooling System p1p1ng 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 during system maintenance or restoration.

Susceptible locations depend on plant and system configuration, such as stand-by versus operating conditions.

(continued)

B 3.4.10-5 Revision w

RHR-High Water Level B 3.9.8 BASES

, or an inoperable but functional RHR shutdown

icooling subsystem.

ACTIONS sufficient Decay heat removal by ambient losses can be considered as, or contributing to, the alternate A......l (continued) functional availability of the alternate method must be reconfirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

This will en ure continued heat removal capability.

Alternate decay heat removal methods are available t o erators for review and preplanning in the unit ope ating procedures.

The equired cooling capacity of the alternate method should be t-------~

method capability.

prudent choice Alternate methods that can be used include (but are not limitedto)

B.l. B.2. B.3. and B.4 LaSalle 1 and 2 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.l, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending the loading of irradiated fuel assemblies into the RPV.

Additional actions are required to minimize any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.

These administrative controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly isolated when a need for secondary containment isolation is indicated).

(continued)

B 3.9.8-3 Revision B

BASES ACTIONS I sufficient 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)

LaSalle 1 and 2 A......l (continued)

RHR-Low Water Level B 3.9.9

, or an inoperable but functional RHR shutdown cooling subsystem.

Alternate decay heat removal methods are available to the operators for review and preplanning in the unit o erating procedures.

The r ~~~ ired cooling capacity of the alternate method(s) should be'-¥:

1--.;.;;...;;;.....;...;.;..;;;..;;;;.""""'-.;;..;;...;;;....._;;.r Condition A is modified by a Note allowing separate Condition entry for each inoperable RHR shutdown cooling subsystem.

This is acceptable since the Required Actions for this Condition provide appropriate compensatory actions for each inoperable RHR shutdown cooling subsystem.

Complying with the Required Actions allow for continued operation.

A subsequent inoperable RHR shutdown cooling subsystem is governed by subsequent entry into the Condition and application of the Required Actions.

B.l. B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.

These administrative controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device.

(continued)

B 3.9.9-3 Revision B

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.5 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 B 3.4.10-3 B 3.4.10-4 B 3.9.8-3 B 3.9.9-3

BASES (continued)

ACTIONS RHR Shutdown Cooling System - Hot Shutdown B 3.4.9 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 LCO Note 2, the inoperable subsystem must be restored to OPE:RABU: status without delay. In this oondition, the remaining OPE:RABLE:

subsystem oan provide the neoessary deoay heat removal. 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 capabilities1' (continued)

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

_J provide assurance of continued heat removal capability.

NMP2 B 3.4.9-3 Revision 0, 9 (A109)

BASES ACTIONS RHR Shutdown Cooling System - Hot Shutdown B 3.4.9 A.1. A.2. and A3 (continued)

The required cooling capacity of the alternate method should be ensured by verifying (by calculation or demonstration)

I sufficient 1--->~ its capability 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)

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.

NMP2 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), aoo a combination of an ECCS pump and S/RVs':'

or an inoperable but functional RHR shutdown cooling subsystem.

alternate methods of decay heat removal, it is also required to reduce the reactor coolant temperature to the point where MODE 4 is entered.

B.1. B.2. and B.3

~<:---~IC~-~1~

. C~-:§2=::!. a~n~d~C~-~3_J 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.

B 3.4.9-4 (continued)

Revision G

BASES (continued)

ACTIONS RHR Shutdown Cooling System - Cold Shutdown B 3.4.10 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 provided 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.

With one of the two RHR shutdown cooling subsystems inoperable except as permitted by LCO Note 2, the remaining subsystem is capable of providing the required decay heat removal. However, the overall reliability is reduced.

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.

I sufficient

~

The required cooling capacity of the alternate method should......-----------.

be ensured by verifying (by calculation or demonstration)

, or an inoperable NMP2 its capability to maintain or reduce temperature. Decay but functional RHR heat removal by ambient losses can be considered as, or shutdown cooling contributing to, the alternate method capability. Alternate subsystem.

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), aA&-a combination of an ECCS pump and S/RVs':'

(continued)

B 3.4.10-3 Revision G

B.1 BASES ACTIONS (continued)

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 NMP2 RHR Shutdown Cooling System - Cold Shutdown B 3.4.10 B.1 and B.2

-EE<:---"11c~.1~a~n~d~C~.2~1 With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as is permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service. This will provide the necessary circulation for monitoring coolant temperature.

The 1 hour1.157407e-5 days 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 system 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.

SR 3.4.10.1 This Surveillance verifies that one RHR shutdown cooling subsystem or recirculation pump is in operation and circulating reactor coolant.

The required flow rate is determined by the flow rate necessary to provide sufficient decay heat removal capability. The Surveillance t

Frequency is controlled under the Surveillance Frequency Control Program.

SR 3.4.10.2 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.

(continued)

B 3.4.10-4 Revision 0, 4a (A150), 44 (A152)

RHR-High Water Level B 3.9.8 BASES

.------A'"""'-=C..... T....

I O

.... N

...... S......._ ____

...., A.1 (continued)

Decay heat removal by ambient losses can be considered as, or method should be ensured by verifying (by oaloulation or contributing to, the alternate demonstration) its oapability to maintain or reduce method capability. Alternate temperature.

the methods that can be used include Spent Fuel Pool Cooling and Cleanup System, Alternate Decay (but are not limited to)

Heat Removal System, eF-the Reactor Water Cleanup System

'"'------------'"--------' operating with the regenerative heat exohanger bypassed or

....-----------------.. in combination with the Control Rod Drive System or

, or an inoperable but functional RHR shutdown cooling subsystem.

NMP2 Condensate/Feed System The method used to remove the decay e

e mos prudent choice based on unit B.1. B.2. B.3. and B.4 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.1, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending the loading of irradiated fuel assemblies into the RPV.

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

These administrative controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly isolated when a need for secondary containment isolation is indicated).

This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons. It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it (continued)

B 3.9.8-3 Revision G

BASES ACTIONS 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)

, or an inoperable but functional RHR shutdown cooling subsystem.

NMP2 RHR - Low Water Level B 3.9.9 sufficient A.1 (continued)

Alternate decay heat emoval methods are available to the operators for review nd preplanning in the unit operating procedures. The re

red cooling capacity of the alternate method(s) should be demonstration) their capability to maintain or reduce temperature. For example, this may include the use of the Spent Fuel ol Cooling and Cleanup System, Alternate Decay Heat Removal System, or the Reactor Water Cleanup System operating with the regenerative heat exchanger bypassed or in combination with the Control Rod Drive System or Condensate/Feed System. The method used to remove decay heat should be the most p dent choice based on unit conditions.

Condition A is modified by a Note allowing separate Condition entry for each inoperable RHR shutdown cooling subsystem. This is acceptable since the Required Actions for this Condition provide appropriate compensatory actions for each inoperable RHR shutdown cooling subsystem.

Complying with the Required Actions allow for continued operation. A subsequent inoperable RHR shutdown cooling subsystem is governed by subsequent entry into the Condition and application of the Required Actions.

B.1. B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.1, additional actions are required to minimize any potential fission product release to the environment. This includes ensuring secondary containment is OPERABLE, one standby gas treatment subsystem is OPERABLE, and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability.

These administrative controls consist of stationing a dedicated operator, who is in continuous communication with the control room, at the controls of the isolation device.

In this way, the penetration can be rapidly isolated when a (continued)

B 3.9.9-3 Revision G

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.6 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 3.4-35 B 3.4-36 B 3.4-37 B 3.4-41 B 3.9-22 B 3.9-26 Peach Bottom Atomic Power Station. Unit 3 B 3.4-35 B 3.4-36 B 3.4-37 B 3.4-41 B 3.9-22 B 3.9-26

BASES APPLICABILITY (continued)

ACTIONS PBAPS UN IT 2 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 Additionally, in MODE 2 below this pressure, the OPERABILITY requirements for the Emergency Core Cooling Systems (ECCS)

(LCO 3.5.1, "ECCS-Operating")

do not allow placing the RHR shutdown cooling subsystem into operation.

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."

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.l A. 2 and A. 3 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the i noperab l e subsystem must be restored to OP ERA BLE status wi thout de l ay.

In t hi s cond i t i on, t he rema i ni ng OP ERA BLE subsystem can prov i de the necessary decay heat remova l.

+-h-&

continued B 3.4-35 Revision No. 2-

B.1 BASES ACTIONS 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.

sufficient 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.

PBAPS UN IT 2 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 A.l. A.2. and A.3 (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 tdown cooling subsystem inoperability.

This lishes backup decay heat removal capabilities, similar the requirements of the LCO.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion T1 is based on the decay heat removal function and the probabil of a loss of the available decay heat removal capabilities The required cooling capacity of the alternate method should ensLired by ver i fy i ng (by ca l cLi l at i on or demonstrat i on) its capabi l ity 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 -iJ:.ft4 the Reactor Water Cleanup System*

or an inoperable but functional RHR shutdown cooling subsystem.

to redLice MOD E ~ is entered.

~L 1.

~L 2. and

~L 3

<~-~jC:2*::k1

.~C:2*&:2.~a~nigddC~.3:L_J 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 B 3.4-36 Revision No. -G

BASES ACTIONS SURVEILLANCE REQUIREMENTS PBAPS UN IT 2 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 r

C.1. C.2. and C.3 B. l. B.2. and B.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.

SR 3.4.7.1 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 p1p1ng 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 B 3.4-37 Revision No. +u

BASES ACTIONS sufficient A......l (continued)

RHR Shutdown Cooling System-Cold Shutdown B 3.4.8 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 ensLired by ver i fy i ng (by ca l cLi l at i on or demonstration) its capabi l ity 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 (feed and bleed), -il:-fl-d. the 8.1 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.

Reactor Water Cleanup System. <

I r----;

, or an inoperable but functional RHR PBAPS UN IT 2 B. 1 and B. 2 tjc. 1 and C.2 I shutdown cooling subsystem.

With no RHR shutdown cooling subsystem and no recirculation pump in operation, except as permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service.

This will provide the necessary circulation for monitoring coolant temperature.

The 1 hour1.157407e-5 days 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)

B 3.4-41 Revision No. -G

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

PBAPS UN IT 2 A......l (continued)

RHR-High Water Level B 3.9.7 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 ensure continued heat removal capability.

Alternate e decay heat n unit conditions.

B.3 and B.4 are available to the Operating of the most prudent choice no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.1, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending loading of irradiated fuel assemblies into the RPV.

Additional actions are required to m1n1m1ze any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem for Unit 2 is OPERABLE; and secondary containment isolation capability (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration not isolated that is assumed to be isolated to mitigate radioactive releases.

This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.

It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it must be restored to OPERABLE status.

In this case, a surveillance may need to be performed to restore the component to OPERABLE status.

Actions must continue until all required components are OPERABLE.

continued B 3.9-22 Revision No. -&

BASES ACTIONS 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.

PBAPS UN IT 2 A......l (continued)

RHR-Low Water Level B 3.9.8 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 this 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 ensure continued heat removal capability.

decay heat removal methods are available to the s for review and preplanning in the unit's Operating Procedure For examp l e, t hi s may include the use of the Reactor Water Cl eanup System, operating with the regenerat i ve heat exc hanger bypassed.

The method used to remove decay heat should be the most prudent choice based on unit conditions.

B.l. B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem for Unit 2 is OPERABLE; and secondary containment isolation capability (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration that is assumed to be isolated to mitigate radioactive releases.

This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.

It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it must be restored to OPERABLE status.

In this case, the surveillance may need to be performed to restore the component to OPERABLE status.

Actions must continue until all required components are OPERABLE.

continued B 3.9-26 Revision No. B

BASES APPLICABILITY (continued)

ACTIONS PBAPS UN IT 3 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 Additionally, in MODE 2 below this pressure, the OPERABILITY requirements for the Emergency Core Cooling Systems (ECCS)

(LCO 3.5.1, "ECCS-Operating")

do not allow placing the RHR shutdown cooling subsystem into operation.

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."

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.l. A. 2. and A. 3 With one required RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by LCO Note 2, the inoperab l e subsystem must be restored to OPERABLE status wi t hout de l ay.

In t hi s cond i t i on, the remaining OPERABLE subsystem can provide the necessary decay heat removal.

f.ft.e continued B 3.4-35 Revision No. 3

BASES ACTIONS 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.

sufficient RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 A.l. A. 2. and A.3 (cont inued )

overall reliability is reduced, however, because a single failure in the OPERABLE subsys tem could result in reduced RHR shutdown cooling capability.

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

required RHR shutdown coo ling subsystems ino rable, an alternate method of decay heat removal must be pro ided in addition to that provided for the initial RHR shutdown ooling subsystem inoperability.

Thi s re-establis es backup decay heat removal capabilities, similar to th requirements of the LCO.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time *s based on the decay heat removal function and the probabilit of a lo ss of the available decay heat removal capab ilitie s 1--~~T1he required cooling capacity of the alternate method shou ld b ensured by ver i fy i ng (by ca l cul ati on or demonstration) its capabi l ity to maintain or reduce temperature.

Decay heat removal by ambient lo sses can be considered as, or contr ibuting to, the alternate method capability.

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

, or a~ inoperable but functional RHR shutdown 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.

3

. cooling subsystem.

8. 1. 8. 2. and 8. 3 C.1. C.2. and C.3 With no RHR shutdown cooling subsys tem 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 wi thout delay.

Until RHR or recirculation pump operation is re-established, an alternate method of reactor coo lant circulation must be placed into serv ice.

Thi s will provide the necessary circu lation for monitoring coo lant temperature.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time i s based on the coolant circulation function and is modified suc h that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i s applicable separate l y for each occurrence in vo l ving a lo ss of coolant continued B 3.4-36 Revision No. B

BASES ACTIONS SURVEILLANCE REQUIREMENTS PBAPS UN IT 3 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 f C.1, C.2, and C.3 B.1. B.2. and B.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.

SR 3.4.7.1 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 (SOC) System p1p1ng and components have the potential to de velop 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)

B 3.4-37 Revision No. 2-8

BASES ACTIONS A......l (cont inued )

RHR Shutdown Cooling System-Cold Shutdown B 3.4.8 removal capabilities.

Furthermore, ver ification 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.

I ff The required cooling capacity of the alternate method shou ld

._s_u_ic_i_e_n_t ____ _:----~ ensured by ver i fy i ng (by ca l cu l ati on or demonstration) 8.1 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.

PBAPS UN IT 3 its capabi l ity to maintain or reduce temperature.

Decay heat removal by ambient lo sses can be considered as, or contr ibuting to, the alternate method capability.

Alternate methods that can be used include (but are not limited to) the Condensate/Main Steam Systems (feed and bleed), -a-ttt=!- the Reactor Water Cleanup System7

~~::------~

I

8. 1 and 8. 2

~C.1 and C.2 I

, or an inoperable but functional RHR shutdown cooling subsystem.

With no RHR shutdown cooling subsys tem and no recirculation pump in operation, except as permitted by LCO Note 1, and until RHR or recirculation pump operation is re-established, an alternate method of reactor coolant circulation must be placed into service.

Thi s 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 i s modified suc h that the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i s applicable separate l y for each occurrence involving a lo ss of coolant circulation.

Furthermore, verifica tion 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.

Thi s will provide assurance of continued temperature monitoring capabi lity.

During the period when the reactor coolant is being circulated by an alternate method (other than by the required RHR shutdown coo ling 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)

B 3.4-41 Revision No. B

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

PBAPS UN IT 3 A......l (continued)

RHR-High Water Level B 3.9.7 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 ensure continued heat removal capability.

decay heat removal methods are available to the for review and preplanning in the unit's Operating Procedure For examp l e, thi s may include th e use of t he Reactor Water Cl eanup System, opera t ing wi t h t he re generat i ve heat exc hanger bypassed.

The method used to remove the decay heat should be the most prudent choice based on unit conditions.

B.1. B.2. B.3. and B.4 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.1, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending loading of irradiated fuel assemblies into the RPV.

Additional actions are required to m1n1m1ze any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem for Unit 3 is OPERABLE; and secondary containment isolation capability (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration not isolated that is assumed to be isolated to mitigate radioactive releases.

This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.

It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it must be restored to OPERABLE status.

In this case, a surveillance may need to be performed to restore the component to OPERABLE status.

Actions must continue until all required components are OPERABLE.

continued B 3.9-22 Revision No. B

BASES ACTIONS 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.

PBAPS UN IT 3 A......l (continued)

RHR-Low Water Level B 3.9.8 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 this 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 ensure continued heat removal capability.

decay heat removal methods are available to the for review and preplanning in the unit's Operating Procedur For examp l e, t hi s may include the use of the Reactor Water Cl eanup System, operating with the regenerat i ve heat exc hanger bypassed.

The method used to remove decay heat should be the most prudent choice based on unit conditions.

B.l. B.2. and B.3 With the required decay heat removal subsystem(s) inoperable and the required alternate method(s) of decay heat removal not available in accordance with Required Action A.l, additional actions are required to minimize any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem for Unit 3 is OPERABLE; and secondary containment isolation capability (i.e., one secondary containment isolation valve and associated instrumentation are OPERABLE or other acceptable administrative controls to assure isolation capability) in each associated penetration that is assumed to be isolated to mitigate radioactive releases.

This may be performed as an administrative check, by examining logs or other information to determine whether the components are out of service for maintenance or other reasons.

It is not necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the components.

If, however, any required component is inoperable, then it must be restored to OPERABLE status.

In this case, the surveillance may need to be performed to restore the component to OPERABLE status.

Actions must continue until all required components are OPERABLE.

continued B 3.9-26 Revision No. B

ATTACHMENT 3 Markup of Proposed Technical Specifications Bases Pages (Information Only) 3.7 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 B 3.4.8-4 B 3.4.8-5 B 3.9.8-2 B 3.9.8-3 B 3.9.9-2 B 3.9.9-3

BASES APPLICABILITY (continued)

IA.1. A.2. and A.3 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.

RHR Shutdown Cooling System-Hot Shutdown B 3.4.7 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 3.9.8, "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

-t--

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.

With one RHR shutdown cooling subsystem inoperable for decay heat removal, except as permitted by the LCO Note, the iAoperable subsystem must be restored to OPERABLE status without delay (Required ActioA A. l).

IA this coAditioA, the remaiAiAg OPERABLE subsystem caA provide the Aecessary decay heat removal.

~

overall reliability is reduced, ho *,~ever 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-:-2-~

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

This re-estaDlishes backup decay heat removal capabilities, similar to th e 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 bas,d on the decay heat removal function and the probabilit v of a loss of the available decay heat removal capabilities >V (continued)

Quad Cities 1 and 2 B 3.4.7-3 Revision 2-

BASES ACTIONS A.1. A.2. and A.3 RHR Shutdown Cooling System-Hot Shutdown B 3.4.7

, or an inoperable but functional RHR shutdown cooling subsystem.

A.1. A.2. A.3. A.4 and A.5 (continued)

I sufficient The required cooling capacity 1--~b-e\\¥,ett-5-tr~::t-t't-¥--'t-t~-f-'ll"+-A-tj-+tt-¥-ea-tt:ilTh:t'E-'t-tttt-trF--t1t~~-t:-F-..:tt+e-tt-r its capab il ity to maintain or reduce temperature.

Decay heat removal by ambient losses can be consider d as, or contributing to, the alternate method capabili y.

Alternate methods that can be used include (but are not imited to) the Condensate/Feed and Main Steam Systems, th Reactor Water Cleanup System in the decay heat removal mode (by itself or using feed and bleed in combination ith the Control Rod Drive System or Condensate/Feed Sys em), Uft!. a combination of an ECCS pump and relief valve(s).

In addition, with both RHR shutdown cooling subsystems inoperable, an alternate method of reactor coolant circulation must be placed into service (Required Action

~ A-: ).

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 t ~ perature IA 3 1 and pressure must be periodically monitored to ens e proper f1rnc tj on of the apt; rnate method (Required Action ~ ).

The 'A31 once per hour Com tion ~ e is deemed appropriate.

~

Required Actions ~

and A=:-4 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.

Due to the potent i all y reduced reliability of the alternate methods of decay heat remova l, it is also required to reduce t he reactor coo l ant temperature to the point where MODE 4 i s entered (Requ i red Act i on A. 5).

/

I

.--~~~~~~~~~~~~~~~~~......_~~~~~~~~~~~~~~----. (continued)

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.

Quad Cities 1 and 2 B 3.4.7-4 Revision 2-

BASES ACTIONS

!sufficient A......l (continued)

RHR Shutdown Cooling System-Cold Shutdown B 3.4.8 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.

1--~___.I~~

~ - required cooling capacity of the alternate method should be"Ver1sured by ver i fy i Ag (by ca l culat i oA or deA'loAstrat i oA) its capabi l ity 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), il-l't4 a combination of an ECCS pump and a safety/relief valve7 or an inoperable but functional RHR shutdown cooling subsystem.

A.2 and A.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 one of the required RHR shutdown cooling subsystems), 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)

Quad Cities 1 and 2 B 3.4.8-4 Revision B

BASES ACTIONS SURV ILLANCE REQU REMENTS RHR Shutdown Cooling System-Cold Shutdown B 3.4.8 A.2 and A.3 (continued)

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.

SR 3.4.8.1 Verifying the correct alignment for manual and power operated valves in the two RHR shutdown cooling subsystems' flow paths 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 8.1 lftherequiredalternate position prior to locking, sealing, or securing.

A valve that can be manually (remote or local) aligned is allowed to method(s)ofdecayheat be in a non-RHR shutdown cooling position provided the valve removalcannotbe can be repositioned.

This SR does not require any testing verifiedwithinonehour, or valve manipulation; rather, it involves verification that immediateactionmustbe those valves capable of potentially being mispositioned are takentorestorethe in the correct position.

This SR does not apply to valves inoperableRHRshutdown that cannot be inadvertently misaligned, such as check cooling subsystem(s) to valves.

The Survei 11 ance Frequency is controlled under the operable status. The Survei 11 ance Frequency Control Program.

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.

SR 3.4.8.2 RHR Shutdown Cooling System p1p1ng 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 (continued)

Quad Cities 1 and 2 B 3.4.8-5 Revision B-

BASES LCO (continued)

APPLICABILITY ACTIONS RHR-High Water Level B 3.9.8 necessary portions of the RHR Service Water System must be capable of providing cooling water to the RHR heat exchanger.

Management of gas voids is important to RHR 1......-

Shutdown Cooling System OPERABILITY.

-f Additionally, the RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown cooling mode for removal of decay heat.

Operation (either continuous or intermittent) of one subsystem can maintain and reduce the reactor coolant temperature as required.

One RHR shutdown cooling subsystem must be OPERABLE in MODE 5, with irradiated fuel in the RPV and with the water level

~ 23 feet above the top of the RPV flange, to provide decay heat removal.

RHR shutdown cooling subsystem requirements in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS).

RHR shutdown cooling subsystem requirements in MODE 5 with irradiated fuel in the RPV and with the water level < 23 ft above the RPV flange are given in LCO 3.9.9, "Residual Heat Removal

( RHR)-Low Water Level."

A.l. A.2. and A.3 With no RHR shutdown cooling subsystem OPERABLE, an alternate method of decay heat removal must be provided within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

In this condition, the volume of water above the RPV flange provides adequate capability to remove decay heat from the reactor core.

However, the overall reliability is reduced because loss of water level could result in reduced decay heat removal capability.

The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is based on decay heat removal function and the probability of a loss of the available decay heat removal capabilities.

Furthermore, verification of the functional availability of the alternate method must be reconfirmed every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

This will ensure continued heat removal capability.

Alternate decay heat removal methods are available to the operators for review and preplanning in the unit operating procedures.

The required cooling capacity of the alternate method should bef Asured by verifyiAg (by calculatioA or

1lsufficient I (continued)

Quad Cities 1 and 2 B 3.9.8-2 Revision B-

BASES RHR-High Water Level B 3.9.8

, or an inoperable but

irunctional RHR 1----

ACTIONS 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 A.1. A.2. and A.3 (continued) shutdown cooling subsystem the in combination with the Co Rod Drive System or Condensate/Feed System method used to remove the decay heat should be the most prudent choice based on unit conditions.

~a-~_

e_n_o_t _Hm_it_e_d_t_

o) ____ __, Additionally, if no RHR Shutdown Cooling System is OPERABLE, an alternate method of coolant circulation is required to be established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 the required RHR shutdown cooling subsystem), the reactor coolant temperature must be periodically monitored to ensure proper functioning of the alternate method.

The once per hour Completion Time is deemed appropriate.

B.1. B.2. B.3. and B.4 If no RHR shutdown cooling subsystem is OPERABLE and an alternate method of decay heat removal is not available in accordance with Required Action A.1, actions shall be taken immediately to suspend operations involving an increase in reactor decay heat load by suspending loading of irradiated fuel assemblies into the RPV.

Additional actions are required to m1n1m1ze any potential fission product release to the environment.

This includes ensuring secondary containment is OPERABLE; one standby gas treatment subsystem is OPERABLE; and secondary containment isolation capability is available in each associated penetration flow path not isolated that is assumed to be isolated to mitigate radioactive releases (i.e., one (continued)

Quad Cities 1 and 2 B 3.9.8-3 Revision B

BASES LCO (continued)

APPLICABILITY ACTIONS RHR-Low Water Level B 3.9.9 Additionally, each RHR shutdown cooling subsystem is considered OPERABLE if it can be manually aligned (remote or local) in the shutdown cooling mode for removal of decay heat.

Operation (either continuous or intermittent) of one subsystem can maintain and reduce the reactor coolant temperature as required.

Two RHR shutdown cooling subsystems are required to be OPERABLE in MODE 5, with irradiated fuel in the RPV and with the water level < 23 ft above the top of the RPV flange, to provide decay heat removal.

RHR shutdown cooling subsystem requirements in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS).

RHR shutdown cooling subsystem requirements in MODE 5 with irradiated fuel in the RPV and with the water level

~ 23 ft above the RPV flange are given in LCO 3.9.8, "Residual Heat Removal

( RHR)-Hi gh Water Level."

A.l. A.2. and A.3 With one of the two required RHR shutdown cooling subsystems inoperable, the remaining subsystem is capable of providing the required decay heat removal.

However, the overall reliability is reduced.

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 the 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 ensure continued heat removal capability.

Alternate decay heat removal methods are available to the operators for review and preplanning in the unit operating procedures.

The required cooling capacity of the alternate methodls) should b ~eAs,,e<l By 'epifyiA§ (By eale*latieA OP 1

(continued)

!sufficient I Quad Cities 1 and 2 B 3.9.9-2 Revision B

BASES ACTIONS RHR-Low Water Level B 3.9.9

, or an inoperable but functional RHR shutdown cooling subsystem A.1. A.2. and A.3 (continued) demons t ra ti on) th ei r capability to maintain or reduce tempera ure.

For examp l e, thi s may include the use of

~D-e_c_a_y_h_e_a_t-~-e~m-o_v_a_l_b_y~~---. Fuel Pool Coolingye-r-Reactor Water Cleanup System tt+t-f-'-f'T+++-t+ti-ambient losses can be h'i th t he regenerat i v'e heat e)(C han ger bypassed or in considered as, or combination with the Control Rod Drive System/Feed Syste The method used to remove decay heat should be the most contributing to, the alternate prudent choice based on unit conditions.

method capability. Alternate methodsthatcanbeused In addition, with both required RHR subsystems inoperable, include(butarenotlimited an alternate method of coolant circulation is required to be

.... to....;.) _________ __. established within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (Required Action A.2).

This will provide necessary circulation for monitoring 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 must be periodically monitored to ensure proper functioning of the alternate method (Required Action A.3).

The once per hour Completion Time is deemed appropriate.

Condition A is modified by a Note allowing separate Condition entry for each inoperable required RHR shutdown cooling subsystem.

This is acceptable since the Required Actions for this Condition provide appropriate compensatory actions for each inoperable required RHR shutdown cooling subsystem.

Complying with the Required Actions allow for continued operation.

A subsequent inoperable required RHR shutdown cooling subsystem is governed by subsequent entry into the Condition and application of the Required Actions.

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

(continued)

Quad Cities 1 and 2 B 3.9.9-3 Revision B

v t e Letter Sequence Request
EPID:L-2020-LLA-0077, Technical Specifications Task Force (Approved, Closed)
Initiation Request Acceptance Supplement Administration Questions Answers Results Approval Other:
MONTHYEAR2020-05-01 [Table View]

RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems: Difference between revisions

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1.0 DESCRIPTION

2.0 ASSESSMENT

3.0 REGULATORY ANALYSIS

4.0 ENVIRONMENTAL CONSIDERATION

5.0 REFERENCES

3.4.7 APPLICABILITY

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RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems: Difference between revisions

Latest revision as of 03:27, 13 December 2024

Text

Subject:

Reference:

1.0 DESCRIPTION

2.0 ASSESSMENT

3.0 REGULATORY ANALYSIS

4.0 ENVIRONMENTAL CONSIDERATION

5.0 REFERENCES

3.4.7 APPLICABILITY

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3.4.8 APPLICABILITY

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