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Text

Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements
	ML20323A248
Person / Time
Site:	Dresden, Clinton, Quad Cities, LaSalle
Issue date:	11/18/2020
From:	Simpson P; Exelon Generation Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML20324A090	List: ML20323A254; RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements;
References
	RS-20-115, TSTF-582
	Download: ML20323A248 (85)
	v • d • e

4300 Winfield Road Warrenville, IL 60555 Exelon Generation 630 65 7 2000 Office RS-20-115 10 CFR 50.90 November 18, 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 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 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265

Subject:

Application to Revise Technical Specifications to Adopt TSTF-582, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements"

References:

1. Letter from Victor G. Cusumano (U.S. NRC) to Technical Specifications Task Force , "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582 , Revision 0, 'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020

2. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582 , Revision 0, 'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process," dated October 9, 2020

November 18, 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 Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2, 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 NRG-approved Industry/Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," (Reference 1), and also incorporates the variation described in Reference 2. 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 that the amendment be reviewed under the Consolidated Line Item Improvement Process (CLllP). Approval of the proposed amendment is requested within six months of completion of the NRC's acceptance review. 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 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.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 18th day of November 2020.

Respectfully, Pa+/-tR ~

Patrick R. Simpson 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)

November 18, 2020 U.S. Nuclear Regulatory Commission Page 3 cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station (Dan Tesar)

Illinois Emergency Management Agency - Division of Nuclear Safety

ATTACHMENT 1 Description and Assessment

1.0 DESCRIPTION

Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," 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, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station , Units 1 and 2, Technical Specifications (TS). The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions in TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The proposed changes also include the variation described in TSTF-583 and discussed in Reference 3.

2.0 ASSESSMENT 2.1 Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a letter dated August 13, 2020 (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station , Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.

EGC verified that the required ECCS injection/spray subsystem can be aligned and the pump started using relatively simple evolutions involving the manipulation of a small number of components. These actions can be performed in a short time (less than the minimum Drain Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) from the control room following plant procedures.

2.2 Variations 2.2.1 Proposed TS Changes to Adopt TSTF-583-T, "TSTF-582 Diesel Generator Variation" TSTF-582, "RPV WIC Enhancements," states:

The ECCS injection/spray subsystem required to be operable by LCO 3.5.2 must be capable of being manually started as defense-in-depth against an unexpected draining event. The changes in TSTF-542 did not assume automatic actuation of the ECCS subsystem . TS 3.5.2, Required Action D.1 requires an additional method of water injection and that the required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. However, LCO 3.5.2 does not assume that the onsite electrical power source will start automatically on an ECCS or loss of power signal.

Page 1

ATTACHMENT 1 Description and Assessment LCO 3.8.2, "AC Sources - Shutdown ," requires one offsite circuit and one diesel generator to be operable in Modes 4 and 5. SR 3.8 .2.1 lists the TS 3.8.1, "AC Sources -

Operating," SRs that are applicable in Modes 4 and 5. In an oversight in TSTF-542 , the TS 3.8 .1 SRs that test automatic start and loading of a diesel generator on an ECCS or loss of offsite power signal were not excluded from SR 3.8.2 .1.

TSTF-582 revises Technical Specification (TS) 3.8.2, "AC Sources - Shutdown," Surveillance Requirement (SR) 3.8.2 .1, to exclude SRs that verify the ability of the diesel generators to automatically start and load on an ECCS initiation signal or loss of offsite power signal.

The NRC Safety Evaluation for TSTF-582 (ADAMS Accession No. ML20223AOOO, dated, August 13, 2020), Section 3.6, "Alternating Current Sources - Shutdown, STS 3.8.2," states:

STS 3.5.2, "Reactor Pressure Vessel Water Inventory Control (RPV WIC)," does not require automatic ECCS initiation to mitigate a draining event in Modes 4 and 5, and the ECCS initiation signal related to the automatic ECCS initiation is removed from the STS .

Because the automatic ECCS initiation and related ECCS initial signal in Modes 4 and 5 are eliminated , the automatic start of the DG on an ECCS initiation signal is not required in Modes 4 and 5 . ... [T]he NRC staff finds that STS 3.5.2 provides enough time from the onset of the [loss of offsite power] LOOP event for the operator to manually start the DG required to supply power to the water injection equipment to mitigate the draining event in Modes 4 and 5. In addition, STS 3.5.2 does not require the automatic initiation of the ECCS injection/spray subsystem or the additional method of water injection . Therefore, since STS 3.5.2 allows enough time to manually start the DG and the equipment for water injection, the NRC staff finds that the automatic start and loading of the DG are not necessary on a LOOP signal or LOOP concurrent with an ECCS initiation signal to mitigate a draining event in Modes 4 and 5.

Furthermore, the NRC staff notes that other events postulated in Modes 4 and 5 (e.g. ,

FHA, waste gas tank rupture) and during movement of [recently] irradiated fuel assemblies in the [primary and secondary containment] do not assume a LOOP event or an automatic ECCS initiation .

TSTF-582 did not include all of the TS changes needed to reflect that TS 3.8.2 should not require automatic start and loading of a diesel generator within 12 to 13 seconds (12 seconds for Clinton, and 13 seconds for Dresden, LaSalle, and Quad Cities) on an ECCS initiation signal or a loss of offsite power signal.

TS 3.3.8.1 , "Loss of Power (LOP) Instrumentation," is applicable in Modes 1, 2, and 3, and when the associated diesel generator is required to be operable by TS 3.8.2. TSTF-582 revised TS 3.8.2 to no longer require automatic start and loading of a diesel generator on a loss of offsite power signal. Consequently, the LOP instrumentation that generates the loss of offsite power signal should not be required to be operable when the diesel generator is required to be operable by TS 3.8.2. The Applicability of LCO 3.3.8.1 is revised to not include the specified condition "When the associated diesel generator is required to be OPERABLE by LCO 3.8.2 , 'AC Sources - Shutdown'."

Page 2

ATTACHMENT 1 Description and Assessment

TS SR 3.8.1.7 and SR 3.8 .1.15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1 .16 (for Dresden and Quad Cities), require that the DG starts from standby or hot conditions, respectively, and achieve required voltage and frequency within 12 to 13 seconds (12 seconds for Clinton , and 13 seconds for Dresden, LaSalle, and Quad Cities). The 12 to 13 second start requirement supports the assumptions in the design basis LOCA analysis.

This capability is not required during a manual diesel generator start to respond to a draining event, which has a minimum Drain Time of one hour. Therefore, SR 3.8.1.7 and SR 3.8.1 .15 (for Clinton and LaSalle), and SR 3.8.1.8 and SR 3.8.1.16 (for Dresden and Quad Cities), are added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1.

These SRs are not included under SR 3.8.2.1.

Clinton, Dresden, and Quad Cities TS SR 3.8.1.18 state "Verify interval between each sequenced load block is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed . The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1. This SR is not included under SR 3.8.2.1

LaSalle TS SR 3.8 .1 .18 state "Verify interval between each sequenced load block, for Division 1 and 2 DGs only, is ~ 90% of the design interval for each load sequence time delay relay." TSTF-582 retained SR 3.8.1.18 as a test that must be met but not performed . The relay logic schemes that perform a function equivalent to a load sequencer are only used for the automatic start and loading of the diesel generator and are not used during a manual diesel generator start. Therefore, SR 3.8.1.18 is added to the list of TS 3.8.1 SRs that are not applicable under SR 3.8.2.1 . This SR is not included under SR 3.8 .2.1 The TS 3.8.2 LCO Bases were not updated by TSTF-542 or TSTF-582 to reflect that automatic start and loading of a diesel generator is not required. The LCO 3.8.2 and SR 3.8.2.1 Bases are revised to reflect the TS requirements .

This variation provides consistency within the TS after incorporating the TSTF-582 changes to SR 3.8.2 .1.

As an editorial improvement, SR 3.8.2.1 is revised to list the TS 3.8.1 SRs that are applicable instead of listing the TS 3.8 .1 SRs that are not applicable. The SR 3.8.2.1 Bases are not affected and explain why the omitted TS 3.8.1 SRs are not applicable to TS 3.8.2.

Page 3

ATTACHMENT 1 Description and Assessment 2.2.2 Editorial Variations The Clinton, Dresden, LaSalle, and Quad Cities TS utilize different numbering and titles than the Standard Technical Specifications on which TSTF-582 and TSTF-583-T were based . Table 1 describes the differences between the plant-specific TS numbering and titles and the TSTF-582 and TSTF-583T numbering and titles. These differences are administrative and do not affect the applicability of TSTF-582 to these plant's TS.

Table 1. TSTF-582 and TSTF-583-T BWR4 and BWRG Numbering and Title Variations TSTF-582 (BWR4) Dresden Quad Cities Table 3.3.5.2-1 Table 3.3.5.2 System Table 3.3.5.2 System

- RHR System Isolation nomenclature difference nomenclature difference

- Shutdown Cooling - RHR Shutdown Cooling System (SOC) Isolation System (SOC) Isolation SR 3.5.2 .5 Numbering difference Numbering difference

- SR 3.5.2.4 - SR 3.5.2.4 -

SR 3.5.2.7 Numbering difference Numbering difference

- SR 3.5.2 .6 - - SR 3.5.2.6 TS 3.6 .1.3 Condition F Numbering difference Numbering difference

- TS 3.6.1.3 Condition E - - TS 3.6.1 .3 Condition E TSTF-583-T (BWR4) Dresden Quad Cities SR 3.8.1.9 Numbering difference Numbering difference

- SR3.8.1.10 - SR 3.8.1.10 SR3.8.1.10 Numbering difference Numbering difference

- SR 3.8.1.11 - SR 3.8.1.11 SR3.8.1.14 Numbering difference Numbering difference

- SR3.8.1.15 - SR 3.8.1.15 SR3.8.1.16 Numbering difference Numbering difference

- SR3.8.1.17 - SR 3.8.1.17 TSTF-582 (BWR6) Clinton LaSalle Table 3.3.5.2-1 N/A System nomenclature RHR System Isolation difference

- RHR Shutdown Cooling System Isolation TS 3.3 .6.1 Required Action Numbering difference N/A J.2 - TS 3.3.6.1 Required Action M.2 Page4

ATTACHMENT 1 Description and Assessment 2.2.3 Other Variations 2.2.3.1 Clinton, Dresden, LaSalle, and Quad Cities Additional Variations EGC is proposing the following additional variations from the TS changes described in TSTF-582. The variations are described in Table 2. These variations do not affect the applicability of TSTF-582 to the proposed license amendments.

Table 2. TSTF-582 BWR4 and BWRG Other Variations TSTF-582 (BWR4) Dresden Quad Cities Comments SR 3.3.5.2.3 No equivalent SR No equivalent SR No changes made TS 3.6 .1.3 Condition G No equivalent No equivalent No changes made condition condition TS 3.6 .1.3 Condition H No equivalent No equivalent No changes made condition condition TSTF-582 (BWR6) Clinton LaSalle Comments TS 3.3 .5.2 Conditions D No equivalent No equivalent No changes made and E Condition E Conditions D and E SR 3.3.5 .2.3 No equivalent SR No equivalent SR No changes made SR 3.5.2.7 No equivalent SR N/A No changes made 2.2.3.2 Clinton Specific Variation EGC is proposing the following variations from the TS changes described in TSTF-582 for Clinton Power Station. EGC is proposing to delete TS 3.3 .6.1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 . These are not included in TSTF-582. With the TSTF-582 deletion of TS 3.3.6.1 M.2 for Clinton (J.2 in TSTF-582), TS 3.3.6. 1 Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 are no longer applicable. These Clinton specific actions are no longer applicable after adoption of TSTF-542 (Reference 5, 6, and 7). Required Actions M.3.1, M.3.2, M.3.3, and M.3.4 should be deleted with the deletion of TS 3.3.6.1 M.2. This plant specific variation does not impact the applicability of TSTF-582 to the Clinton TS.

Page 5

ATTACHMENT 1 Description and Assessment

3.0 REGULATORY ANALYSIS

3.1 No Significant Hazards Consideration Determination Analysis Exelon Generation Company, LLC (EGC), requests adoption of TSTF 582 , "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements." The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions that were incorporated into the plant TS when adopting TSTF-542 , Revision 2, "Reactor Pressure Vessel Water Inventory Control." TSTF-582 includes the following changes to the TS:

1. The Drain Time definition is revised to move the examples of common mode failure mechanisms to the Bases and seismic events are no longer considered a common mode failure mechanism .

2. The Drain Time definition exception from considering the Drain Time for penetration flow paths isolated with manual or automatic valves that are "locked, sealed, or otherwise secured" is revised to apply the exception for manual or automatic valves that are "closed and administratively controlled."

3. The TS are revised to permit placing an inoperable isolation channel in trip as an alternative to declaring the associated penetration flow path incapable of automatic isolation .

4. A Surveillance Requirement (SR) that requires operating the required Emergency Core Cooling System (ECCS) injection/spray subsystem for at least 10 minutes through the recirculation line , is modified to permit crediting normal operation of the system to satisfy the SR and to permit operation through the test return line.

5. Dresden, Unit 2 and 3 share secondary containment structures between units. LaSalle, Unit 1 and 2 share secondary containment structures between units. Quad Cities, Unit 1 and 2 share secondary containment structures between units. The TS Actions are revised to recognize that an operable secondary containment and operable secondary containment isolation valves satisfy the Required Actions.

6. The Clinton, Dresden, LaSalle , and Quad Cities designs contain additional isolation instrumentation functions based on low RPV water level that could be credited when calculating Drain Time. Those functions are added to the required functions in TS 3.3.5 .2.

7. TS 3.8.2, "AC Sources - Shutdown ," SR 3.8 .2.1, is revised to not require SRs that test the ability of the automatic diesel generator to start in Modes 4 and 5. Automatic ECCS Page 6

ATTACHMENT 1 Description and Assessment initiation in Modes 4 and 5 was eliminated in TSTF-542. This was an oversight in TSTF-542.

8. TS 3.3 .6.1, "Primary Containment Isolation Instrumentation," Required Action J.2 (J .2 for LaSalle and M.2 for Clinton) is deleted . This action is no longer applicable after adoption of TSTF-542. This was an accidental omission in TSTF-542. This change is made for clarity and has no effect on the application of the TS .

9. The Applicability of TS 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," is revised to delete the phrase, "When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, 'Primary Containment Isolation Instrumentation'." This makes TS 3.6.1.3 only applicable Modes 1, 2, and 3. Following adoption of TSTF-542, no functions in LCO 3.3.6 .1 are applicable outside of Modes 1, 2, or 3. The Actions and SRs are revised to reflect this change. These changes are made for clarity and have no effect on the application of the TS.

10. The TS are revised to use wording and to define acronyms in a manner consistent with the remainder of the TS. These changes are made for consistency and have no effect on the application of the TS.

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 incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." Draining of RPV water inventory in Mode 4 (i.e., cold shutdown) and Mode 5 (i.e., refueling) is not an accident previously evaluated and , therefore , revising the existing TS controls to prevent or mitigate such an event has no effect on any accident previously evaluated. RPV water inventory control in Mode 4 or Mode 5 is not an initiator of any accident previously evaluated. The existing and revised TS controls are not mitigating actions assumed in any accident previously evaluated .

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

Page 7

ATTACHMENT 1 Description and Assessment

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 incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The event of concern under the current requirements and the proposed change is an unexpected draining event. The TS have contained requirements related to an unexpected draining event during shutdown for over 40 years and this event does not appear as an analyzed event in the Updated Final Safety Analysis Report (UFSAR) for any plant or in the NRC's Standard Review Plan (NUREG- 0800). Therefore, an unexpected draining event is not a new or different kind of accident not considered in the design and licensing bases that would have been considered a design basis accident in the UFSAR had it been previously identified.

None of the equipment affected by the proposed change has a design function described in the UFSAR to mitigate an unexpected draining event in Modes 4 or 5, although the equipment may be used for that purpose. Therefore, the proposed amendment will not change the design function of the affected equipment. The proposed change will affect the operation of certain equipment, such as the manual initiation function and related instrumentation to permit initiation of the required ECCS injection/spray subsystem, and the control of valves credited for preventing a draining event. However, these changes provide adequate protection to prevent or mitigate an unexpected draining event and do not create the possibility of a new or different kind of accident due to credible new failure mechanisms, malfunctions, or accident initiators not considered in the design and licensing bases.

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

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

Response: No The proposed change incorporates operating experience and corrects errors and omissions that were incorporated into the plant TS when adopting TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The safety basis for the RPV WIC requirements is to protect Safety Limit 2.1.1.3. The proposed change does not affect any specific values that define a safety margin as established in the licensing basis. The proposed change does not affect a design basis or safety limit, or any controlling value for a parameter established in the UFSAR or the license.

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

Page 8

ATTACHMENT 1 Description and Assessment 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-582, Revision 0, RPV WIC Enhancements,"' dated August28 , 2019

2. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,

'RPV WIC Enhancements' Using the Consolidated Line Item Improvement Process (EPID L-2019-PMP-0199)," dated August 13, 2020

3. Letter from Victor G. Cusumano (U .S. NRC) to Technical Specifications Task Force, "Model Safety Evaluation of Technical Specifications Task Force Traveler TSTF-582, Revision 0,

'RPV WIC Enhancements' and TSTF-583-T, Revision 0, 'TSTF-582 Diesel Generator Variation,' Using the Consolidated Line Item Improvement Process, " dated October 9, 2020

4. NUREG-1433, Standard Technical Specifications, General Electric BWR/4 Plants, Volume 1, Revision 4, dated April 2012 Page 9

ATTACHMENT 1 Description and Assessment

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

6. Letter from Alexander R. Klein (U.S. NRC) to Technical Specifications Task Force, "Final Safety Evaluation of Technical Specifications Task Force Traveler TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control ," dated December 20, 2016

7. Letter from P. Simpson (EGC) to U.S. NRC, "Application to Revise Technical Specifications Following Adoption of TSTF-542, 'Reactor Pressure Vessel Water Inventory Control,"' dated June 18, 2019 Page 10

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 1.0-3 1.0-4 3.3-43a 3.3-43b 3.3-43c 3.3-43d 3.3-44 3.3-51 3.3-52 3.3-78 3.8-19

Definitions 1.1 1.1 Definitions (continued)

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle . These cycle specific limits shall be determined for each re l oad cycle in accordance with Specification 5 . 6 . 5 . Plant operation within these limits is addressed in individual Specifications .

DOSE EQUIVALENT I - 131 DOSE EQUIVALENT I - 131 shall be that concentration of I - 131 (microcuries/gram) that alone would produce the same inhalation CEDE dose as the quantity and isotopic mixture of I - 131 , I - 132 ,

I - 133 , I - 134 , and I - 135 actually present . The inhalation CE DE dose conversion factors used for this calculation shall be those listed in Table 2.1 of Federal Guidance Report 11 , " Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation , Submersion , and Ingestion ," ORNL ,

1989.

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming :

a. The water inventory above the TAF is divided by the limiting drain rate;

b. The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate , or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e g I 8ei8mic e u ent , .l.B-8-& M normal po 1er , Bingle R-Yma-n error ) , for all 1

(co nt inued)

CLINTON 1.0 - 3 Amendment No. ~

Definitions

1. 1 closed and administratively controlled Definitions DRA IN TIME penetrat i on flow paths below the TAF except (continued )

1. Penetration flow paths connected to an int a ct closed system , or isolated by manual or automatic va l ves that are l ocked , sea l ed , G-t- otheri1ise secured in the closed position , b l ank flanges , or other devices that prevent flow of reactor coolant through the penetration flow paths ;

2. Penetration flow paths capable of being isolated by va l ves that will c l ose automatical l y without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water l evel isolation instrumentat i on ; or

3. Penetration flow paths with iso l ation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task ,

who is in continuous communication with t h e control room, is stationed at the controls , and is capab l e of closing the penetration flow path i solation devices without offs i te power .

c. The penetration f l ow paths required to be evaluated per paragraph b ) are assumed to open instantaneously and are not subsequently isolated , and no water is assumed to be subsequently added to the RPV water inventory ;

d. No addit i onal draining events occur ; and

e. Realistic cross - sectional areas and drain rates are used .

A bounding DRAIN TIME may be used in l ieu of a ca l culated va l ue .

EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time i nterval SYSTEM (ECCS ) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until t h e ECCS equipment is capable of performing its safety function (i . e ., the valves travel to t h eir required positions , pump discharge pressures reach their required values , etc .). Times shall include diesel generator starting and sequence loading delays , where applicable . The response time may be meas u red by means of any ser i es of sequential ,

over l app i ng , or total steps so t h at the entire response time is measured .

(co n tinued )

CLINTON 1.0 - 4 Amendment No. ~

RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vesse l (RPV ) Water I nventory Control I nstrumentation LCO 3.3.5.2 The RPV Water I nventory Control instrumentation for each Function in Table 3 . 3 . 5 . 2 - 1 shall be OPERABLE .

APPLICABIL I TY : According to Tab l e 3 . 3 . 5 . 2 - 1 .

ACTIONS

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

Separate Condition entry is al l owed for each channel .

CONDITION REQUIRED ACTION COMPLETION TIME A...- Gf+/-l. .g..:r. ~ QAClAA9la ~ .t.f+/-. C9A9iti9A iA9j;;>Q:f ClQl9 :fQfQ:fQAQQg .i-1:+

~ J J 5 2 f.G-:r-

-t-M QAilAAQl AA :r g qyi:r g g b¥- Initiate action to Immediately ggqyi:rgg Ai;;ti9A place channel in trip .

.a.A4 :rgfg:r9AQ9G .i-1:+

~JJ521 Dec l a r e associated Immed i ately One or more penet r ation flow path (s ) incapable of channels automat i c isolation .

inoperable.

Initiate action to Immediately calcu l ate DRAIN TIME .

G-... AA :rgqyi:rgd b¥-

ggqyi:rgd A i;;ti9A A..-+/-

.a.fi4 :f9f9:f9AQ9g .i-1:+

~JJ521 (co n tinued )

CLINTON 3 . 3 - 43a Amendment No. J.;b.

RPV Water Inventory Contro l Instrumentat i on f 3.3.5.2 ACTIONS (cont i nued )

CONDITION REQUIRED ACTION COMPLET I ON TIME

~ Ag. +/-:H'J:Hi+/-:@Q b¥ P-.-1. bl@G l ;;p: @ ~ "'.l'atE!m .;i,. ~

g@qni+/-:E!Q AGtigi:i A-...l. ii:igp@ i::: eildl@

~ +/-:E!fE!+/-:E!!=!GE! Q .i.f+

~ ~ ~ ~ 2 l QR D--.- ~ -the- ~ pYmp .;i,. ~

aHGtiQl=l .t..g. -the-

ypp

i;9: ;;:;; ,:i,gi:i ~

E-.- Ag. :i;sqtii+/-:eci b¥ E-.-J,. gs:;;tg i::: e Gfiirni:iel .t..g. -64 ~

ge q ti i:i; eg AGt i gi:i A-...l. GJi!E gll £l1E :;;tatti:;;

~ :i;efe:i;ei:iGeQ .i.f+

~ ~ ~ ~ 2 l R.- geqni:i;sg AGt i gi:i ~ R.-J,. blsGlei i::: s a:;;:;;gGieiteg Immegiatsl:i' ei:;;:;;gGieit@g ECC£. ii:i:j E!Gtigi:i ,l :;;p:i;ei J' Cgmpletigi:i Hme- G-f- :;;yld.s:i,:;;tem ii:igpe:i;aldle Cgi:ig i tigi:i c, .Q., G-+/-- E AG-t- me-t-.-

CLINTON 3 . 3 - 43b Amendment No. ~

These SRs apply to each Function in RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 SURVE I LLANCE REQUIREMENTS

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

Re-f.e.+/-- .t-G- Tab l e 3 . 3 . 5 . 2 - 1 .t-G- d e t e rmi1:rn ~ .£.Re. ~ .f.G+/-:. ~ EGG.£. F1m.::tig1=1 .

SURVEI LLANCE FREQUENCY SR 3 . 3 . 5 . 2 .l Perform CHANNEL CHECK . I n accordance wi th t h e Surveil l ance Frequency Control Program SR 3.3.5.2.2 Perform CHANNEL FUNCT I ONAL TE ST . In accordance wit h the Surveil l ance Frequency Control Program CLINTON 3 . 3 - 43c Amendment No. ~

RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 Table 3 . 3 . 5 . 2 - 1 (page 1 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE CQNPITIQ11£ MODES OR REQUIRED l<li!:Fl!:l<l!:llC!W OTHER CHANNELS ERGM SPECIFIED PER l<l!:Ql!Il<l!:P £l!J<l11!:IbbMJCI!: ALLOWABLE FUNCTION CONDITIONS FUNCTION .ACTIQ~J A 1 l<l!:Q(!IJ<l!:Ml!:~JT:a' VALUE

.- Jog11 Press " re Cggl:;rnt IHj e stiGH n (bPCI)

oHGl 1.g" Pres:;;nPe Cgre

£pny (1-PC:a')

a'nldsystem:;;

a-.- !< e a st gr .gg ;; 2 1 f; Hi4 p:;;ig u gggg l Prge2rnrg .gg ;; 2 2 1,gp (IHje stiGH Permi:;;:;;i" e)

G-.- bPC:a' PYmp .gg ;; 2 1 ;;; 72Q gpm bliscAargg Flgu .gg ;; 2 2 1,gp (llyp:o gg)

G..- bPCI Pnmp .A .gg d d 2 1 ;;; 9QQ gpm Pigsfis.rge ¥12'7 .gg d d 2 2 bbl'! (ll yp* gg)

~ bPCI !l aH9 bPCI C

a'uldi;;yi;;temg a-.- l<eastr;ir " egggl .gg d d 2 1 f; 494 p:;;ig Pr988 " Hl J,gp .gg d d 2 2 (IHjestiGH Pgr:miggiug )

G-.- 1-PCI Pnmp !l .gg ;; d 2 1 ;;; 9QQ gpm

OH9 1-PCI Pnmp C .gg d d 2 2 Pisslnrge Fl2F -

b2F (llypass)

(continued)

+ei+ Ass2si3tgg PitJ:1 3H !!:CC£ snldsystgm r:gqnir:gg tg }dg QPl!:l<A!lbl!: ldy bCQ d 3 2 , " l'P" \l'J3tgr IHHQHtGP/

Cgi:i.trg l "

CLINTON 3 . 3 - 43d Amendment No. ~

RPV Water Inventory Contro l Instrumentat i on 3.3.5.2 Table 3 . 3 . 5 . 2 - 1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE CQNblITIQN£ MODES OR REQUIRED Fli:Fli:Rli'.NCIW OTHER CHANNELS -FRGM SPECIFIED PER Fli:QTJIF!i:bl £TlF " li:IbPNC!i: ALLOWABLE FUNCTION CONDITIONS FUNCTION JlCTIQN Jl 1 Fli:QTJIF!i:Nli:NT£ VALUE

...._ Migl

! Press11re Cgre

£pr3y (MPC£) £yste111

&-.-- FCIC £tgrage TaAk 4 <b1 , a * .£R -a-]~]"""-'~ 2>-.-+/--1 be " @l b9'! .£R -a-]~]"""-'~ 2~ 2

~ MPC£ Pn111p .£R ~:;~:;_...,.'"'"""2~1 bl i sr;;l:iarge .£R .,,,

] -.--a

]-.-d~ 2,.....-.=-

2 Pre a a " re Migl:!

(llypns )

G-.- MPC£ £yste111 Fl9H 2 1 ~ ?QQ gpm F3te - b91' (llypns )

RHR System Isolation

a. Reactor Vessel ( <> ) 2 in one 2 1 ::". 8.3 inches Water Level - trip Low , Level 3 system Reactor Water Cleanup (RWCU) System

~

Isolation

a. Reactor Vessel ( <> ) 2 in one 2 1 ::". - 48 . 1 Water Level - Low trip inches Low , Level 2 system

+a+ " ssssi3te9 11itl=l aA Rccg s11ssyste111 ret=J:11ireol ts loe QP!i:F " llbli: loy bCQ :; 3 2, " FP" Water IA"eAte;sy C9Atrgl "

Wl=leA MPcg is QP!i:F " llbli: fgr G9111pliaAGe 11itl=l bCQ :; 3 2 , " FP" Water IA" eAtsry C9Atrsl , " aA9 aligAeol ts tl=le FCIC stsrage taAk 'll=lile taAk *1ater level is Ast 11itl=liA tl=le limits gf

£F ] a 2 ]

When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TI ME .

CLINTON 3.3 - 44 Amendment No. ~

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME J . As required by J .l Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Action F . l penetration flow and referenced in path (s) .

Table 3 . 3 . 6 . 1 - 1 .

K. As required by K. l Be in MODE 3 . 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action F . l and referenced in AND Table 3 . 3 . 6.1 - 1 .

K. 2 Be in MODE 4 . 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Required Act i on and associated Completion Time of Condition I or J not met.

L. As required by L. l Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action F . l standby liquid and referenced in control subsystem Table 3 . 3 . 6 . 1 - 1 . inoperable .

OR L.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup System .

M. As required by M. l Initiate action to Immediately Required Action F . l restore channel to and referenced in OPERABLE status .

Table 3 . 3 . 6 . 1 - 1 .

IHitiate aGtiGH .t4 Immeciiately isGlate ~ 1;:es i cilnl

~ 1;:e1+18a l ~

£l::wtciGHH CGGliHg

£ystem snGtiGH ~

~ re21GtGr " essel (continued)

CLINTON 3.3 - 51 Amendment No. ~

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME M. (Continued) Initiat g aQtign .t4 rgstgrg SQQgndary Qgnt;;iinmgnt .t4 QPJi:'.RAJ3I.E: steitns Initiat g aQtign .t4 r g stgr g ' standay ga.& trgatmgnt ~

s agyst:gm .t4 QPE:RAJ3I.E:

11 status Initiat g aQtign .t4 rgstgrg isglatign Qapaaility .i.A ~

r9b{ irgd SQQgnd;;iry 11 Qgntainm g nt 6-00 s g Qgndary Qgntainm g nt aypass p g n g tratign

~ pa-th A-G-t-is g lat 9 d M.--J-. NQ TE:

E+l-t-Pf aH-G ~ -i-&

pgrmissiblg .um:ie-r-administratiug Qm:1trgl Initiat g aQtign .t4 Imm g diat g ly

-G-1-G-&e- ' OOG-r- .i.A -t-fi.e-

.uppe-r. Qgntainmgnt pgrsgnngl d-i+/-- ~

N. As required by N. 1 Isolate the affected Immediately Required Action F . l penetration flow and referenced in path (s).

Table 3 . 3 . 6 . 1 - 1 .

OR N. 2 Suspend movement of Immediately recently irradiated fuel assemblies in the primary and secondary containment.

CLINTON 3.3 - 52 Amendment No. ---2-1-e.

LOP Instrumentat i on 3.3.8.1 3.3 I NSTRUMENTATION 3.3.8.1 Loss of Power (LOP ) Instrumentation LCO 3.3.8.1 The LOP i nstrumentation for each Function in Tab l e 3 . 3 . 8 . 1 - 1 shal l be OPERABLE.

APPLICABIL I TY : MODES 1 , 2 , and 3, ~

Wfi.e-A .:l;.l:i.e aeeocia.t e d di e s e l g e n e ra.tor ~ .i.& r e qtJ.ir e d .t.G b.e-OP:E;g7\fl1.8 b:f I.W ~ g ~ , .'.!.AG £onrc e s - £J:rntdoun "

ACTIONS

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

Separate Condition entry is al l owed for each channel .

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A. 1 Place channel in trip . 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable .

AND A. 2 --------- NOTE ----------

On l y applicable for Funct i ons 1. c , 1 . d ,

1 . e , 2 . c , 2 . d , and 2.e Restore channel to OPERABLE stat u s . 7 days B. Required Act i on and B. l Declare associated DG Immediately associated Completion inop erable .

Ti me not met .

CLINTON 3.3 - 78 Amendment No. ~

AC Sources ~ S hu tdown 3.8.2 SURVE I LLANCE REQUIREMEN TS SURVEI LLANCE FREQUENCY SR 3.8.2.l ------------------- NOTE -------------------- , SR 3.8.1.10,

.Jt:!

~

Th e fol l owing SRs are not re q uired to be per f ormed : SR 3.8 . 1.3 , SR 3 . 8 . 1.9 through SR 3.8.1.14, and

$R ~ g l ll , $R J g l u through SR 3 . 8 . 1 . 16, 6-AG $R J g l a .

--0 The fol lowing SRs ~~ AC sources required to be OPERABLE~ I n accordance are app licable for £.R.g. ~ £pg,-;ifi£atioi:i J g l, gxggpt with appl i cable

$R ~ g l g , $R J g l 16 , $R J g l 17 ' SRs

$R ~ g l lg , 6-AG $R J g l 6Q a-re appli.-;afile SR 3.8.1 .1 SR 3.8.1 .6 SR 3.8.1 .2 SR 3.8.1 .9 SR 3.8.1 .3 SR 3.8.1 .10 SR 3.8.1.4 SR 3.8.1 .14 SR 3.8.1 .5 SR 3.8.1 .16 CLINTON 3 . 8- 19 Amendment No. ~

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 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.6.1.3-5 3.8.2-3

Definitions

1. 1 1.1 Definitions (continued)

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a. The water inventory above the TAF is divided by the limiting drain rate;

b. The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e . § ., seismic eveAt ,

l oss of Aorrna l po *.1er , siA§le hbtrnaA error) ,

for all penetration flow paths below the TAF except:

Penetration flow paths connected to an closed and intact closed system, or isolated by administratively controlled manual or automatic valves that are l ocke9 , sea l e9 , or other **i se seCb1re8 in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration fl ow paths;

2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or

3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.

(continued)

Dresden 2 and 3 1.1-4 Amendment No. 266/259

RPV Water I nventory Contro l I nstrumentation

3. 3. 5. 2 3.3 I NS TRUMENTATION 3.3 . 5.2 Reactor Pressure Vesse l (RPV) Water I nventory Control I nstrumentation LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentation for each Funct i on in Table 3.3.5.2-1 sha l l be OP ERABLE.

AP PLI CAB ILIT Y: According to Tab l e 3.3.5.2-1.

ACTIONS

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

Separate Cond i tion entry is al lowed for each channe l .

CON DIT ION REQU I RED AC TI ON COM PLE TI ON TI ME A.- GAe OF Arn Fe GAflAAe~ s A--.+/-- E:A teF tl:le 6oA9itioA I11m1e9i ete~ J' iAOFJeFaB~e . Fef:eFeAGe9 i A

+a t:i~e J . J . a . ~ 1 f:OF tRe GAaAAe~ .

A.1 I

\¥

.g.._ As BJ' .g....,..+ I nitiate act i on to Immediately

\

Fe~tJiFe9 Re~tJi Fe9 AGtiOA A. 1 place channe l in a Ag Fef:eFeAGe9 i A trip .

+at:i ~e J . J . a . ~ 1.

OR IA.2.1 I it Dec l are associated Immediately A.On e or more channels ~

in ope rable. penetration fl ow path(s) incapable of automatic iso l ation.

A~

B.2 . 2 I nitiate action to Immediately ca l cu l ate DRAIN TIM E.

6 . As Fe~tJi Fe9 gJ1 b----.----+/-- i:n aGe GAaAAe~ i A tFiFJ . 1 AOLiF Re~tJiFe9 AGtioA A. 1 fJA9 Fef:eFeAGe9 i A

+at:i~e J . J . a . 2 1.

(cont i nued)

Dresden 2 and 3 3.3 . 5. 2-1 Amendment No . 2§g/2§1

RPV Water I nventory Contro l I nstrumentation

3. 3. 5. 2 ACTIONS COND IT ION REQUIRED ACTION COMP LETI ON TI ME Q. As FeEjtii reEI B:J' .IJ-.--+/-. Restere GRannel te 24 R8blFS ReEjti ire El AGtien A. 1 OPrnAgLE stattis .

a nEI ref:erenGeEI in

+:a8le ~ . ~ . 9 . 2 1.

E. ReEjti ire El AGtien a nEI -h IJeGlare asseGiateEI l ei,1 +/-mmeEli atel:J' asseGiateEI 6emf)letien flFesstire E66£

+:ime ef: 6enElitien 6 8F i naeGti en,LSfJFa:J' Q net met. SblBS:J' Stem inef)eFa8le .

SURV EILL ANCE REQUIR EMENTS

~These SRs apply to each Function in I

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

Ref:er te Tab l e 3.3.5.2-1 te Eletermine 11RiGR £Rs af)fllY f:er eaGR E66£ ~tinGtien .

SURVEI LLANC E FR EQUENCY SR 3 . 3.5 . 2. 1 Perform CHANNE L CHECK . In accordance with the Survei l lance Frequency Contro l Program SR 3 . 3 . 5.2.2 Perform CHANNE L FUNC TI ONAL TE ST. I n accordance wi t h the Survei l lance Frequency Contro l Program Dresden 2 and 3 3.3 . 5. 2-2 Amendment No . 268/261

RPV Water I nventory Contro l I nstrumentation

3. 3. 5. 2 Table 3 . 3 . 5 . 2-1 (Page 1 of lJ RPV Water Inventory Control Instrumentation APPLICABLE bGNl:llTIGMS MODES R>*rnrnGrn OR OTHER REQUIRED ~

SPECIFIED CHANNELS PER R>Q " IRrn SllR" U bb ' MG> ALLOWABLE FUNCTIO N CONDITIONS FUNCTION ' bTIG~I 0

.1 R>Ql lIR>MDIH VALUE

~ ReaGter Steam Geme ~ L~ . 9 . 2 . 2 ,,; ;J41.7 ~sig Press~re be11 (Permissi,,e)

B-. Gere S~ray P61m~ ~ ~ :i . :i . 8 . 2 . 2 G i s>:~arge

l e" be11 ~ 1 1m~ (al rn) ~a66 l

,..___ be11 Prsss *1rs Geel a Rt IRjeGtieR (bPG I ) Systsm

~ ReaGter Steam Geme ~ ;J.:J.9.2.2 ,,; ;J41.7 ~sig Prsss~re be11 (Psrmissi,,e) be1 I Press 11re Geel a Rt

{)... 4-,----4 ~ ~ ;i . ;i . 9. 2. 2 llG? g~m IRjeGtieR P11m~ lee~ ( 3)

GiSGRarge

1e1 I be11

~

rny~ass)

~ Shutdown Cooling System (SOC) Isolation a . Reactor Vessel Water

~ ( {} ) per trip ~ ;i . ;i . 9. 2. i ~ 2 . 65 inches Level-Low system ~ ;i . ;i . 9. 2. 2

~ 4-. Reactor Water Cleanup System Isolation

a. Reactor Vessel Water

~ ( {} ) per trip ~ ;i . ;i . 9. 2. 1 ~ 2 . 65 inches Level-Low system ~ ;i . ;i . 9. 2. 2 0

sseGiate9 " itR aR .:u:s s~9system re~~ireEJ te 9e GP>R ' H> 9y u:G :l . 9 . 2 , " RP " 'later IR"eRtery (;eRtrel ."

When automatic i solation of the associated pene t ration flow path(sJ is credited in calculat i ng DRAIN TIME .

Dre sden 2 and 3 3 .3 . 5 . 2-3 Amendment No . 256 / 249

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3,

'1Jf1 e A

~

Hie assoc i ate El Eli es e l § e A et at o I" i s I" e q 1:.d I" e El to 13 e OPERABLE B)' LCO 3. 8 . 2, " AC Sotll"ces SFiutElo 'vJA ."

ACTIONS

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. trip.

B. Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)

Time not met. inoperable.

Dresden 2 and 3 3.3.8.1-1 Amendment No. 185/180

PC I Vs 3 . 6 .1. 3 AC TIONS CON DIT ION REQUIR ED AC TIO N COM PLETI ON TI ME

c. (con t inued) C. 2 - - - - - - - -NO TE S- - - - - - - -

1. I so l ation devices in hi gh rad i ation areas may be veri f ied by use of adm i ni strative means.

2. I so l ation devices t hat a re a l ocked, sea l ed, or otherwise secured may be verified by use of ad mi nistrative means .

Ver i fy the affected Once per 31 days penetrat i on fl ow path is i so l ated.

D. MS I V lea kage ra t e D. 1 Restore leakage ra t e 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months not wit hin l im it. to wit hin l i mit .

E. Requ i red Ac ti on and E. 1 Be i n MOD E 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months assoc i ated Comp l et i on Ti me of Cond iti on A, AND B' C, or D no t met ..:i-A-MQg~

+/-' 2 ' 8F d . E. 2 Be i n MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Dresden 2 and 3 3 . 6.1.3-5 Amendment No . 256 / 249

AC Sources-Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One required DG B.1 Suspend CORE Immediatel y inoperable. ALTERATIONS.

B.2 Suspend movement of Immediatel y recently irradiated fuel assemblies in secondary containment.

B.3 Initiate action to Immediately restore required DG to OPERABLE status.

SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1 .17.

SURVEILLANCE REQUIREMENTS FREQUENCY

-+

SR 3.8.2.1 - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - -

The followi g SRs are not required to performed: r~~r.--...+-.--T.---2M+--'7-.e-.--:r--.--:+/-:-1::1----t-tt-H::H:ttl-ft t

~R 2 . g . 1 . 12 , ane ~R 2 . g . 1 . 14 thro~gh

~R 2 . g . i. rn .

The following SRs i------+ ~ AC sources required to be OPERABLE In accordance are applicable for ~Rs of ~pecification 2 . g . 1 , except with applicable

~R 2 . g . 1 . 9 , ~R 2 . g . 1 . 12 , ~R 2 . g . 1 . 19 , SRs

~R 2 . g . 1 . 20 , ane ~R 2 . g . 1 . 21 are applica8 l e .

SR 3.8.1.1 SR 3.8.1.6 SR 3.8.1.2 SR 3.8.1.10 SR 3.8.1.3 SR 3.8.1.11 SR 3.8.1.4 SR 3.8.1.15 SR 3.8.1.5 SR 3.8.1.17 Dre sden 2 and 3 3 .8.2-3 Amendment No. 26g/26 1

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.3 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.5.2-4 3.3.6.1-4 3.3.8.1-1 3.5.1-1 3.5.1-2 3.5.2-2 3.5.2-3 3.5.2-5 3.8.2-4

Definitions

1. 1 1.1 Definitions DOSE EQUIVALENT I-131 30, Supplement to Part 1, pages 192-212, Table (continued) titled, "Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity."

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a. The water inventory above the TAF is divided by the l imiting drain rate;

b. The lim i ting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the dra i n rates through multiple penetration flow paths susceptible to a common mode failu re (e . g ., seismic event , loss of normal

~0 .1er , single ~u1man error) , for all 1

penet rat ion flow paths below the TAF except:

1. Penetration flow paths connected to an closed and administratively intact closed system, or isolated by manual or automatic valves that are controlled l ocked , sea l ed , or 0H1ernise seCblred in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or (continued)

LaSalle 1 and 2 1.1-4 Amendment No. 242/228

RPV Water Inventory Control Instrumentation -+-

3. 3. 5. 2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.2-1.

A.1 Initiate action to place

- channel in trip.

ACTIONS OR

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

Separate Condition entry is a lowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME I

-A-o- 0Ae or more cAaAAels EAter tAe CoAElitioA Imme Eli a tel :Y iAoperable . referCAced i A Taele 3. 3. 5. 2 1 for A. One or more tAe cAaAAel . \!Immediately I

-channels

- -r+----i IV inoperable. '+'

-&-;- As reEJt:li reEl by Declare associated Immediately ReEjuireEl ActioA A. 1 penetration flow aAEl refereAceEl iA path(s) incapable of Taele 3. 3 . 5. 2 1. automatic isolation.

( ~A N~

IQ-/ ,. r Initiate action to calculate Calculate DRAIN TIME.

IA.2.2:t---.~B-: Immediately C. As reEJui red by Place cAaAAel iA trip . 1 ROUP ReEjui r eEl ActioA A. 1 aAEl refereAceEl iA Table 3 . 3 . S. 2 1.

(continued)

LaSalle 1 and 2 3.3.5.2-1 Amendment No. 230/216

RPV Water In ventory Control In strumentation ~

3.3 .5 .2 AC TION S (continued)

CONDITION REQUIRED AC TIO N COMPLETION TIME B. ,ais FeEf td Fee B:Y B-:-+ Res=!:sFe eFiaAAel =!:s 24 AS~FS ReEf~i Fee ,o,e=t:i SA A . 1 OPERABLE s=!:a=!:~s .

a AEl Fefe FeAeeEl i A

=Fasl e 3 . 3 . 5 . 2 1.

E. ReEJ~i Fee P.c=!:i SA a AS f-:-1. Beel a Fe asssci a=!:ee Ifflffleei a=!:el y asssei a=!:ee EGGS i Aj ee=!:i SA 1ls13 Fa :y Gsfflp le=!: i SA =Fiffle sf s~ssys=!:effl iAspeFasle .

GsAElHi SA G SF B AS=!:

m-e+-:-

These SRs apply to each Function in SUR VEILL ANCE REQUIREMENTS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NO TE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

RefeF =!:s Table 3.3.5.2-1 =!:s Ele=!:eFffliAe WAiCA SRs apply fsF eacFI EGGS F~Ac=!:isA .

SURVEI LLANC E FREQUENCY SR 3.3.5.2. 1 Perform CHANN EL CHE CK. I n accordance wi th the Surve i 11 ance Frequency Control Program SR 3.3.5.2.2 Perform CHANNE L FUNCTIONAL TEST. In accordance with the Surveil l ance Frequency Control Program LaSal l e 1 and 2 3.3.5.2-2 Amendmen t No. 230/216

RPV Water I nventor y Control I ns trumentation + -

+

3 . 3 . 5. 2 Table 3. 3. 5. 2- 1 (page 1 of 2)

RPV Water Inve nt ory Control Instrume nt atio n

= = = = = =

APP LI CABLE G8Pl8 IT I8N S MOD ES OR REQU IR ED REFERDIGEB OTHER CHANNE LS -F-R8!4 SPECIFIED PER RE81:1 I RE8 Sl:IRVEI LLMIGE AL LOWABLE FUNCTION CO NDIT IONS FUNCTION AGTI8PI A. l RE81:1 I REMUITS VAL UE h Le .. PFessriFe Gee l aAt IAjeetieA A (LPG!)

aA8 Le .. PFessriFe GeFe S19Fa) ( LPGSJ Sri13s; stems

..r.- ReaeteF Steam .£tf 3. 3. 5. 2. 2 ~ ~

Beme PFessriFe Le ..

(!Ajeeti BA PeFmissi oe)

-&-:- LPGS Prim19 ~ ~ .£tf 3 .3. 5. 2. 2 ~ §I'm a AS Bi sei'1aF§Je ~..+ < 1835 §J l3m Fle .. Le .. (B;13ass)

--:- LPGI Prim13 A ~ ~ .£tf 3 .3. 5. 2. 2 ~ §Jl3m a AS Bi sei'1aF§Je ~..+ < 2111 §I'm Fl s .. Ls .. (B) 13a ss l 4-:- LPGS aA8 LPGI ,', ~ ~ .£tf 3 .3. 5. 2. 2 ~~

lAjeetieA LiAe ~..+

PFessriFe Ls ..

(lAjeetieA PeFmissioe)

~ LPGI B aA8 LPGI G Sri8s) stems

..r.- ReaeteF Steam .£tf 3. 3. 5. 2. 2 ~ ~

Bsme PFessriFe Ls ..

(lAjeetieA PeFmissi.el

-&-:- LPG! Prim13 B .£tf 3.3. 5.2.2 ~ §Jl3m aAS aA8 LPGI Prim13 G < 2111 §I'm Bisei'1aF§Je Fle .. Le .. (B)13ass)

--:- LPG! B aA8 LPG! G .£tf 3.3. 5.2.2 ~ ~

lAjeetisA LiAe PFessriFe Le ..

(lAjeetieA PeFmissi.el (contin ued)

+a-+ Asseeiates .. itR aA EGGS sril3s;stem FeEfriiFe8 te 13e 8PERABLE 13; LG8 3 . 5 . 2 , " RPV ', /ateF !AoeAtef)

GeAtFel . "

LaSal l e 1 and 2 3 . 3 .5.2-3 Amendmen t No. 230/216

RPV Water In ventory Control In strumentation ~

3.3 .5 .2 Table 3 . 3.5.2-1 (page 2 of 2)

RPV Water Inventory Control Instrumentation APPLICABLE co~rn IT ID~Js MODES OR REQUIRED REFERDJCEB OTHER CHANNELS -F-OOM SPECIFIED PER REGl:IIREB Sl:IRVEI LLMICE ALLOWAB LE FUNCTION CONDITIONS FUNCTION ACTION A. 1 RE81:1IREMEMTS VALUE

- Iii §A PFesstJFe Cs Fe S13Fa) ( llPCSl S)steFA 13-7 l l PGS PtlFA/3 ~ 3. 3. 5. 2. 2 > 113 . 2 13si§ Bi seAaF§e PFeSStJFe Iii §A rnnass)

-&-:- l l PCS S) steFA Fl e" ~ 3. 3 . 5. 2. 2 ~~

Rate Le .. (8)13ass) -a-A4

< 219~ §/3FA

[]

~ 4-:- RHR Shutdown Coo li ng Syste m Isolation

a. Reactor Vessel ( !> )

2 in one ~ 3. 3. 5. 2. 1 ;:: 11. 0 Water Leve l - Low, trip ~ 3. 3. 5. 2. 2 inches Level 3 system

~,,.,. Reoctoc Wotec Cleooop (RWC UJ System I solation

a. Reactor Vessel

~ ( !> )

2 in one ~ 3.3. 5.2.2 ;:: - 58. 0 Water Leve l - Low trip inches Low, Level 2 system

+a-+ AssseiateEI .. itfl aA EGGS StlBS)SteFA FetjtJiFeE1 ts 13e OPE 11ABL E B) LCO 3 . 5 . 2 , " IWV '.later lAoeAtSF)

CsAtFe l ."

~) When automatic isolation of the associated penetration f l ow path(s) i s credited in calculat in g DRAIN TIME.

LaSal le 1 and 2 3.3.5.2-4 Amendmen t No. 230 / 2 16

Prima ry Containment I sol ation In strumentation 3 . 3 .6.1 ACT IO NS CON DIT ION REQUIRED ACT IO N CO MPL ET IO N TI ME J. As requ i red by Re qui re d J .l Init i ate action to Immed i at el y Act i on C.l and referenced restore cha nne l to i n Ta bl e 3. 3. 6.1-1. OP ERAB LE st at us .

I Ait i ate aetieA ts IF!HtteEl i a te l )

i se l ate Hie Resi E1 1:1a l li e at Remeva l (R llR ) Sl91:1 tE1e .. A Cee li A§ (S BC) S)ste m.

SURVEI LLANCE REQU I RE ME NTS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOT ES - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

1. Refer to Tab l e 3 . 3.6 . 1- 1 to deter mi ne whi ch SRs ap pl y for eac h Pr imary Contai nme nt Isolat i on Fu nction.

2. Whe n a chan nel is pl aced in an i noperable sta t us so l ely for pe r for mance of requi red Survei l lances , entry in to assoc i ate d Con diti ons and Re qui re d Ac ti ons may be de l ayed f or up to 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s provi ded t he assoc i at ed Fun ct i on mainta i ns isolation capa bi l i ty .

SURVEI LLANCE FR EQ UEN CY SR 3. 3.6 . 1. 1 Perfor m CHANNEL CHE CK . I n accorda nce wit h t he Sur veil l ance Freq uency Co ntrol Progra m

+

SR 3. 3.6 . 1.2 Perfor m CHANNEL FUN CTIO NAL TES T. In accordance wit h th e Survei l lance Fre que ncy Con t ro l Program (cont i nued)

LaSalle 1 and 2 3 . 3 .6.1-4 Amendment No. 200 / 187

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3..., ~

'1Jf1eA Hie associatee eiese l §eAerator (DC) is re~uiree to be OP CRABLE by LCO 3. 8 . 2, "AG Sources Sl'l uteo *,m ."

ACTIONS

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channe l in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. trip.

B. Required Action and B.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

LaSalle 1 and 2 3.3.8.1-1 Amendment No. H 7/133

ECCS-Operating

3. 5. 1 3.5 EMERGENCY CORE COOLING SYSTEMS CECCS), REACTOR PRESSURE VESSEL CRPV)

WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING CRCIC)

SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except ADS valves are not required to be OPERABLE with reactor steam dome pressure ~ 150 psig.

High Pressure Core Spray (HPCS)

ACTIONS

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

LCO 3.0.4.b is not applicable to H-P-G-& .

CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS A. 1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable. subsystem to OPERABLE status.

(continued)

LaSalle 1 and 2 3.5.1-1 Amendment No. 230 / 216

ECCS-Operating

3. 5. 1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. l ligfi PresstH' e Core B.1 Verify by Immediately S~ray ( HPCS+ System administrative means inoperable. RCIC System is OPERABLE when RCIC is required to be OPERABLE.

B.2 Restore HPCS System 14 days to OPERABLE status.

C. Two low pressure ECCS C.1 Restore one low 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months injection/spray pressure ECCS subsystems inoperable. injection/spray subsystem to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, or C not met.

E. One required ADS valve E.1 Restore required ADS 14 days inoperable. valve to OPERABLE status.

F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition E not met.

(continued)

LaSalle 1 and 2 3.5.1-2 Amendment No. 196/183

RPV Water Inventory Control .+----

3. 5. 2 ACTIONS (continued)

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

- I CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.1 Verify secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and ~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . containment boundary is capable of being established in less than the DRAIN TIME.

C.2 Verify each secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

-i(SGT)I C.3 Verify one sta y 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months gas treatment /

subsystem is capable of being placed in operation in less than the DRAIN TIME.

(continued)

LaSalle 1 and 2 3.5.2-2 Amendment No. 230 / 216

RPV Water In ventory Control ..+--

3 .5 .2 AC TION S (continued)

COND ITION REQUIRED AC TION COMP LETION TIME D. DRAIN TIME < 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . D.1 - - - - - - -NOTE- - - - - - - -

Required ECCS injection/spray subsystem or additional method of water injection sh a 11 be capab le of operating without off site electrical power.

Initiate action to Immediately establish an additional method of water inj ect i on wit h water sources capab l e of maintaining RPV water l eve l > TAF for

'.'. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

AND D.2 Initi ate action to Immediately establish secondary conta inment boundary.

AND D. 3 Initiate action to Immediately isolate each

!automatically or }-----____ secondary containment

penetration flow path r---__ , or verify it can be I ~ manually isolated from the control room.

D.4 Initi ate a~

verify one staA~~Y Immediately

§as treatmCAt subsystem is capable of being placed in operat i on.

(cont in ued)

LaSal le 1 and 2 3.5.2 -3 Amendmen t No. 230/216

NOTES

1. Operation may be through the test return line.

2. Credit may be taken for normal system RPV Water In ventory Control operation to satisfy this SR. 3 .5 .2 SURV EILL ANC E 0 EQUIREMENTS (cont inu ed)

SURVE ILLANC E FREQUEN CY

-&ff 3. 5. 2. 5 -

'"ITC

~

-I---

p~ 8t PeEjtd PeEI t8 ee lflet f e P S:'J'Stelfl ~'eAt f 1 8111' i:iaHis ei:ieAeEI l::!ASeP aEllfli Ai s=l:Pa=t i 'i'e eeA=l:Pe i .

\I e Pi f:,' , feP He PeEj l: ! i PeEI EGGS i Aj ee=t i 8A1'SFJPa:'7' Sl::!B5:'7'5 t elfl , eae A lfla Al::!a 1 ,

i:ie 1~e P ei:iePa=te EI , a AEI al: ! te lfl a=tie 1 ~a 1 1 ~e i A He 1

f 1 8~1 13aH , Hat i 5 Aet iee l<eEI , sea i eEI , 8P

+/-A aeeePdaAee 11~i tAHe Sl::!P~' ei 11 aAee

~PeEfl::!eAE :'7'

+-

eHe P~vi se seel::!PeEI i A 13 es i tieA , i 5 i A He Ge At Pei PPe§Palfl eeP Peet i:iesitieA .

t

~

SR 3.5.2. Operate the required ECCS i njection/spray In accordance subsys tem through the reci rcul ati on lin e for with the

~

~ 10 minutes. Survei 11 ance Frequ ency Control Program SR 3 . 5.2 . Verify each valve credited for automatically In accordance isolating a penetration fl ow path actuates with the

~ to the isolation position on an actual or s imulat ed i so l at i on s ig nal.

Survei 11 ance Frequ ency Control Program SR 3.5.2 . .g - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - -

Vessel injection/spray may be excluded.

~ -------------------------------------------

Verify the required ECCS injection/spray In accordance s ubsystem can be manually operated. with the Survei 11 ance Frequency Control Program LaSal le 1 and 2 3.5.2 -5 Amendmen t No. 23 0/2 16

AC Sources-Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. Required offsite D.1 Declare associated Immediately circuit or DG of LCO standby gas treatment Item d. inoperable. subsystem, control room area filtration subsystem, and control room area ventilation air conditioning subsystem inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 - - - - - - - - - - - - - - - - - - -NOTE-& - - - - - - - - - - - - - - - - - - -

+.:- The following SRs are not required to , SR 3.8.1.10, be performed: SR 3.8.1.3, SR 3.8.1.9 SR 3.8.1.14, and tAFS~§A SR 3 . 8 . 1 . 11 , SR 3 . 8 . 1 . 13 tAFS~§A SR 3.8.1.16, SR 3 . 8 . 1 . 18 , UftE!.

SR 3 . 8 . 1. 19 .

~ SR 3 . 8 . 1 . 12 aA8 SR 3 . 8 . 1 . 19 are As t Fe ~~i Fe G te Be ffi et .

The following SRs f.&r AC sources required to be OPERABLE, In accordance are applicable for SRs ef S13ee if ieatieA 3 . 8 . l , eJ(eqit with applicable SR 3 . 8 . 1 . 8 , SR 3 . 8 . 1 . 17 , aA8 SR 3 . 8 . 1 . 20 , SRs a Fe a1313l i casl e .

SR 3.8.1.1 SR 3.8.1 .6 SR 3.8.1.2 SR 3.8.1 .9 SR 3.8.1.3 SR 3.8.1 .10 SR 3.8.1.4 SR 3.8.1 .14 SR 3.8.1.5 SR 3.8.1 .16 LaSalle 1 and 2 3.8.2-4 Amendment No. 230 / 216

ATTACHMENT 2 Markup of Proposed Technical Specifications Pages 2.4 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 REVISED TECHNICAL SPECIFICATIONS PAGES 1.1-4 3.3.5.2-1 3.3.5.2-2 3.3.5.2-3 3.3.8.1-1 3.5.2-2 3.5.2-4 3.5.2-5 3.5.2-6 3.6.1.3-1 3.6.1.3-4 3.8.2-5

Definitions

1. 1 1.1 Definitions (continued)

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a. The water inventory above the TAF is divided by the limiting drain rate;

b. The limiting drain rate i s the larger of the drain rate through a s ingle penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e . g ., seismic eveRt ,

l oss of Rormeil poi,ier , siRgle hblmeiR error) ,

for all penetration flow paths below the TAF except:

1. Penetration flow paths connected to an intact closed system, or i so lated by closed and administratively controlled manual or automat ic va l ves that are l ockeEi , seei l eEi , or otheni'i se secblreEi in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2. Penetration flow paths capab le of being isolated by valves that wi ll close automatically with out offsite power prior to the RPV water le vel being equal to the TAF when actuated by RPV water le ve l isolation instrumentation; or

3. Penetration flow paths with is olation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who is in continuous commun ication with the control room, i s stat ioned at the controls, and is capable of closing the penetration flow path i solat ion device without offsite power.

(continued)

Quad Cities 1 and 2 1. 1-4 Amendment No. 279/274

RPV Water I nventory Control I nstrumentation 3.3 . 5.2 3.3 I NS TRUMENTATI ON 3 . 3 . 5.2 Reactor Pressure Vesse l (RPV) Water I nventory Contro l I nstrumentat i on LCO 3.3.5.2 The RPV Water Inventory Contro l instrumentat i on for each Funct i on in Table 3.3.5.2 - 1 shal l be OPERAB LE.

AP PLI CAB ILIT Y: According to Tab l e 3.3.5.2- 1 .

ACTIONS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NO TE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Separate Cond i tion entry is al lowed for each channel.

A.1 Initiate action to place channel in trip CON DIT ION OR COMP LETI ON TI ME

/Jr.. 0Ae 8P lfl8Pe cl9aAAel s A-:- EA:f:et" =E 19 e CeAE1it:ieA IlfllfleE1i at: el y i Ae13 n a 131 e . PefereAceE1 i A A. One or more Tas le 3 . 3 . 5. 2 1 fep rllmmediately I r channels inoperable.

.J He el9aAAel .

JV '4 B-:- As PeEjui PeE1 B:Y £-:-+ Dec l are assoc i ated Immediate l y ReEjui PeE1 ,01c=EieA A . 1 penetration fl ow a As Pe:fePeAces i A I A~.11 path(s) incapable of c

Ta sle 3 . 3 . 5. 2 1. automatic isolation.

~ f Initiate action to calculate IA.2.2 H ~ -B-ti- Cal cul a=Ee DRA I N TI ME. Immed i ate l y

c. As PeEjUi PCS B)' -:-+ Place CAaAAel i A fPij3 . 1 A8UP ReEjUiPeS Ac=EieA A. 1 a AE1 PefePeAeeE1 i A

i:a 81 e 3 . 3 . 5 . 2 1.

D. As PeEjUi PeE1 B)' ~ Resf:epe el9aAAel f; 0 2q A8UPS ReEjuiPe8 Act:ieA A. 1 OPERABLE st:a t:us .

a AE1 PefePeAeeE1 i A Tasle 3 . 3 . 5 . 2 1.

(continued) I Quad Ci t i es 1 and 2 3.3.5.2-1 Amendment No. 273/268

RPV Water I nventory Control I nstrumentation 3.3 . 5.2 ACTIONS COND IT ION REQUI RED ACTION COM PLE TI ON TIM E E. ReEjtl i FEEi Aet i sA a AEl f-:4. Deel a Fe assseiateEI l S\i' l A'IA'leEl i a tel y J assseiateEI GSA'if3 l et i SA f3FESSl:lFe EGGS /

f i ffie Sf GsAElitisA G SF i Ajeeti SA 11 s13 Fa:,*

D ASt ffiet . StlBS:)'Steffi i As13eFa l=Jl e .

rJThese SRs apply to each Function in I

SURV EILL ANC E REQ UIR EMENTS

-)

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

~ ef:eF ts Tab l e 3.3.5.2-1 ts EleteFA'liAe ld ~i e~ SRs a1313 l y f:sF eae~ EGGS FtlAetisA .

SURV EI LLANC E FREQU ENCY I

SR 3.3.5 . 2 . 1 Perform CHANNE L CHECK . In accordance with the Surve i 11ance

-)

Frequency Control Program ..

SR 3.3.5.2 . 2 Perform CHANNEL FUNCTIONAL TE ST. In accordance with the Survei 11ance Frequency Control Program Quad Ci t i es 1 and 2 3.3.5.2-2 Amendment No. 273/268

RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3 . 3.5 . 2-1 (Page 1 of 1)

RPV Wat e r Inventory Control Instrumentatio n APPLICABLE G8~18 I TI 8N S MODES REFERUIGEB OR OTHER REQU I RED fiWM SPECIFIED CHANNELS PER RE88IRE9 S8R"EI LL ' NGE ALLOWABLE FUNCTIO N CONDITIONS FUNCTIO N AGT I 8N P . l RE88IREMENTS VAL UE h Ge Fe S13Fa; S; stelll tt7 Reaete1- Stealll Bellle 5-lt 3. 3 . 5. 2. 2 P1 esst:H'e Le (Pe:lllissi.el tr. GeFe S13Fa) P~lllf3 5-lt 3. 3 . 5. 2. 2 Bi SEAaF§e Fl e Ls (8)13assl b Le .. P1 ess~1 e Geel a19t IAjeetieA (LPG!) S;stelll tt7 ReaeteF Stealll Bellle 5-lt 3. 3 . 5. 2. 2 PFess~Fe Le ..

(PeFl!lissi el tr. Le Press~Fe GeelaAt +--!7tt 5-lt 3. 3 . 5. 2. 2 IAjeeti SA P~lllf3 le e13 (al Bi SEAaF§e Fl e Le (B;13assl RHR Shutdown Cooling System (SOC) Isolation

a. Reactor Vessel Water per trip 5-lt 3. 3 . 5. 2. 1 ~ 3. 8 inches Level-Low system 5-lt 3. 3 . 5. 2. 2

~ 4..,. Reactor Water Cleanup (RWCUJ System Isolatio n i

a. Reactor Vessel Water per trip 5-lt 3. 3 . 5. 2. l ~ 3. 8 inches Level-Low system 5-lt 3. 3 . 5. 2. 2

' sseeiateEI itA aA EGGS s~BS)Stelll Fe~~i FEEi te se 8PER ' BLE B) LG8 3 . 5 . 2 , " RP " llateF IA eAtSF) GeAtFel . "

When automatic isolation of the associated pene t ration flow path(s) is credited in calculating DRAIN TIME .

Quad Cities 1 and 2 3.3.5.2-3 Amendment No. 273 / 268

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1 -1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, WAeA tAe associated diesel geAerator is reqHired to be OPERABLE by LCO 3 . 8 . 2 , " AC SoHrces SAHtdmm ."

ACTIONS

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

Separate Condition entry is all owed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. trip.

B. Required Action and B.1 Declare associated Immediately associated Completion diesel generator (DG)

Time not met. inoperable.

Quad Cities 1 and 2 3.3.8.1-1 Amendment No. 199/195

RPV Water Inventory Control ~

3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. DRAIN TIME < 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.1 Verify secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and ~ 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . containment boundary is capable of being established in less than the DRAIN TIME.

C.2 Verify each secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months containment penetration flow path is capable of being isolated in less than the DRAIN TIME. ~(SGT) I C.3 Verify one sta / 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

(continued)

Quad Cities 1 and 2 3.5.2-2 Amendment No. 273 / 268

RPV Water Inventory Control t 3.5.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) D.3 Initiate action to Immediately isolate each secondary containment penetration flow path or verify it can be

!automatically or f-------~-' manually isolated from the control room.

D.4 Initiate action to Immediately verify one st aA~~ Y ga s treatmeAt ~.L."::..---r1:SGT I subsystem is capable of being placed in operation.

E. Required Action and E.l Initiate action to Immediately associated Completion restore DRAIN TIME to Time of Condition C or ~ 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

D not met.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME~ 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . In accordance with the Survei 11 ance Frequency Control Program (continued)

Quad Cities 1 and 2 3.5.2-4 Amendment No. 273 / 268

RPV Water Inventory Control +-

3. 5. 2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for the required ECCS injection/ In accordance spray subsystem, the: with the Survei 11 ance

a. Suppression pool water level is Frequency

~ 8.5 ft; or Control Program

b. Contaminated condensate storage tank(s) water volume is~ 140,000 available gallons.

SR 3.5.2.3 Verify, for the required ECCS In accordance 'I' injection/spray subsystem, locations with the susceptible to gas accumulation are Survei 11 ance sufficiently filled with water. Frequency Control Program

-R 3 . 5 . 2 . ~

Net l"etji:1i l"e E1 te s e FA et fel" sys t eFA 'o'eAt fl 8'oJ

~a t ~ s e ~ e A e E1 ~ A E1 el" aE1FAi Ai stPat i ve ceAtl"e l .

VeP ify , fe l" t~ e l"e ~~i l"e E1 EGGS IA acc e PE1aA ce

+

iAj ec tieA /s ~ P a y s ~s sys t e fFI , eac~ FF1a A ~al , *,;i tA Hi e

~e 'oJCI" e~el"ate E1 , aAE1 a~teFAat i c 'wa l ve iA Hie S~l"vei ll aAce fl 8\1' ~atA , tAat is Aet l ecke E1 , sea l eE1 , el" Fl"e~~eAcy et~el"wise sec~PeE1 i A ~ esitieA , is iA t~e GeAtl"e l Pl"e §l"aFA cel"l"ect ~ esitieA .

(continued)

Quad Cities 1 and 2 3.5.2-5 Amendment No. 273 / 268

NOTES

1. Operation may be through the test return line.

r In ventory Control 3 .5. 2

-r ISR 3.5.2.4 I 2. Credit may be taken for normal system I operation to satisfy this SR.

REQU I/REI I SURVEI LLANCE FREQUENCY

'Y

-&R- 3 . 5. 2. 5 Operate the required ECCS injection/spray In accordance subsystem t A P S~§A tA e Pec iP c ~latieA liA e with the for ~ 10 minutes. Survei 11 ance Frequency

~- Control Program SR 3.5.2.~----------------------+-------

-&R- 3 . 5. 2. 6 Verify each valve credited for In accordance _____

automatically isolating a penetration flow with the path actuates to the isolation position on Surveil lan ce an actual or simulated isolation signa l . Frequency Control Program ISR 3.5.2.6 I 3 . 5. 2. 7 - - - - - - - - - - - - - - - - - - -NOTE- - - - - - - - - - - - - - - - - - - -

Vessel injection/spray may be excluded.

Verify the required ECCS injection/spray In accordance subsystem can be manually operated. with the Survei 11 ance Frequency Control Program

========================================================== +-'

Quad Cities 1 and 2 3.5.2-6 Amendmen t No. 273 / 268

PC I Vs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves CPCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, W~eR associate~ iRstr~meRtatioR is re~~ire~ to ~e OPERAgLE f)er LCD 2 . 2 . 8 . 1 , " Primary CoRtaiRmeRt IsolatioR I RstrnmeRtati OR ."

ACTIONS

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

1. Penetration flow paths may be unisolated intermittently under administrative controls.

2. Separate Condition entry is allowed for each penetration flow path.

3. Enter app l icable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter app l icable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ---------NOTE-------- A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except Only app l icable to penetration flow path for main steam penetration flow paths by use of at least l in e with two or more one closed and PC I Vs. de-activated automatic valve, closed manual valve, 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main One or more blind flange, or steam line penetration flow paths check valve with flow with one PCI V through the valve inoperab l e for reasons secured.

other than Condition D. AND (continued)

Quad Cities 1 and 2 3.6.1.3-1 Amendment No. 199/195

PC I Vs 3 . 6 . 1.3 AC TI ONS CON DIT ION REQU IRED AC TI ON COM PLE TI ON TI ME

c. (con t inued) C. 2 - - - - - - - - NOT ES- - - - - - - -

1. I so l at i on dev i ces in high rad i ation areas may be verif i ed by use of adm i ni s t rat i ve means .

2. I so l at i on devices that are locked, sea l ed, or oth erw i se secured may be verified by use of administrat i ve mea ns .

Verify th e affec t ed Once per 31 days penetra t ion fl ow path i s i solated .

D. MS I V leakage rate D. 1 Restore leakage ra t e 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months no t with i n li mit. to withi n l i mit .

E. Required Action and E. 1 Be in MODE 3 . 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Comp l et ion Time of Cond iti on A, AND B' C, or D no t met-+A-MQQi; +/-, 2 , er 3 . E.2 Be i n MOD E 4 . 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Quad Ci t i es 1 and 2 3 . 6.1.3-4 Amendment No . 273/ 268

AC Sources-Shutdown 3.8.2 SR 3.8.1.3, SR 3.8.1.10, SR 3.8.1.11, SR 3.8.1.15, and SR 3.8.1.17.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 t

~

The following SRs f.ef'- AC sources required to be OPERABLE t-J:T.e. In accordance are applicable for SRs ef SfJcci fi ca ti eA 3 . 8 . 1 , CJ\CCfJt with applicable SR 3 . 8 . 1 . 9 , SR 3 . 8 . 1 . 13 , SR 3 . 8 . 1 . 19 , SRs -t-SR 3 . 8 . 1 . 20 , aA8 SR 3 . 8 . 1 . 21 , ape afJfJl i casl e .

SR 3.8.1.1 SR 3.8.1.6 SR 3.8.1.2 SR 3.8.1.10 SR 3.8.1.3 SR 3.8.1.11 SR 3.8.1.4 SR 3.8.1.15 SR 3.8.1.5 SR 3.8.1.17 Quad Cities 1 and 2 3.8.2-5 Amendment No. 273/268

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 3.3-122a B 3.3-122b B 3.3-122c B 3.3-122d B 3.3-122e B 3.3-122f B 3.3-122g B 3.3-122h B 3.3-122i B 3.3-122j B 3.3-168 B 3.3-169 B 3.3-225 B 3.3-228 B 3.3-229 B 3.5-17 B 3.5-18 B 3.5-19 B 3.5-22 B 3.5-23 B 3.5-24 B 3.8-35 B 3.8-36 B 3.8-39

RPV Water Inventory Control Instrumentation B 3.3.5.2 B 3.3 INSTRUMENTATION B 3.3 . 5 . 2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation BASES BACKGROUND The RPV contains penetrations below the top of the active fuel (TAF) that have the potential to drain the reactor coolant inventory to below the TAF. If the water level should drop below the TAF , the ability to remove decay heat is reduced , which could lead to elevated cladding temperatures and clad perforation . Safety Limit 2 . 1 . l . 3 requires the RPV water level to be above the top of t he active irradiated fuel at all times to prevent such elevated cladding temperatures .

Technical Specifications are required by 10 CFR 50 . 36 to include limiting safety system settings (LSSS) for variables that have significant safety functions . LSSS are defined by the regulation as " Where a LSSS is specified for a variable on which a safety limit has been placed , the setting must be chosen so that automatic protective actions will correct the abnormal situation before a Safety Limit (SL) is exceeded ."

The Analytical Limit is the limit of the process variab l e at which a safety action is initiated to ensure that a SL is not exceeded. Any automatic protection action that occurs on reaching the Analytical Limit therefore ensures that the SL is not exceeded . However , in practice , the actual settings for automatic protection channels must be chosen to be more conservative than the Analytical Limit to account for instrument loop uncertainties related to the set t ing at which the automatic protective action would actually occur.

The actual settings for the automatic isolation channels are the same as those established for the same functions in MODES 1 , 2 , and 3 in +/-rG.Q. ;;J ;;J 5 1 , " I!:merr;;rerH:;y GG..re. C.:wliHr;;T

£ystem (I!:CC£ ) I HstnameHtatiGH 1 " G-.:i:: LCO 3 . 3 . 6 .1, " Primary Containment Isolation instrumentation. "

With the unit in MODE 4 or 5 , RPV water inventory control is not required to mitigate any events or accidents evaluated in the safety analyses . RPV water inventory control is required in MODES 4 and 5 to protect Safety Limit 2 . 1 . 1 . 3 and the fuel cladding barrier to prevent the release of radioactive material should a draining event occur. Under the definition of DRAIN TIME , some penetration flow paths may be excluded from the DRAIN TIME calculation if they will be isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation .

(continued)

CLINTON B 3.3 - 122a Rev i sion No . ~

RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES BACKGROUND The purpose of the RPV Water Inventory Contro l (continued) Instrumentation i s to suppo r t the requirements of LCO 3 . 5 . 2 ,

" RPV Water Inventory Control , " and the definition of DRA I N TIME . There are functions that ~ r e qt1ir e 9 .f.G-T m:urnal iHitiatioH G--T- operatioH G..t: .t.f+e EGG.£. iHj e .::tioH/e:pray gyJdgye:t s m r s qt1ir e 9 .t4 ~ OP.KRAJ;JJ;.,l!;'. b:f J..G.Q. ~ .a.HQ ~

fnH>::tioHe ~ support automatic iso l ation of Residua l Heat Removal subsys t em and Reac t or Water Clean u p system penetration flow path ( s ) on low RPV water level .

-+/-Re- RW Wa-t-9-r- IHu e Htory CoHtrol IHe:trt11+1 e HtatioH eYJd)dOrte:

ops ratioH G..t: J,.o.w. pre e:e:yr g ~ ~ (J;.,PC£ ), J,.o.w. prs e:e:t1r e

.::oolaHt iHj e .::tioH (J;.,PCI ), .a.HQ ~ pr e e:e:t1r e ~ ~

(FIPC£ ) ~ gqnip1+19Ht iH u ol u gg .w.i.tf+/- ~ G..t: ~ gygtgmg .;i,..g.

ggggrilds9 .i.H- .t.f+e ~ .f.G-T J..G.Q. ~ 5 ~

APPLICAB LE With the unit in MODE 4 or 5 , RPV water inventory co n trol is SAFETY not required to mitigate any events or accidents evaluated ANALYSES , LCO , in the safety analyses . RPV water invento r y con t rol is and APPLICAB I LI TY required in MO DE S 4 and 5 to protect Safe t y Limit 2 . 1 . l . 3 and the fuel c l adding barr i er to prevent t he release of radioactive material shou l d a draining event occur .

A double - e n ded gui l lotine break of the Reactor Coolant considered System (RCS ) is not in MODES 4 and 5 due t o the r n reduced RCS pressure , reduced p ipin stresses , and ducti l e considered piping systems . I nstead , an event is poe:tt1lat e 9 i n which a siHgle operator ~ G--T- initiating event a l lows draining of the RPV water inventory through a sing l e penetration flow path with the highest f l ow rate , or the s u m of the drain rates through mu l tiple penetration f l ow paths suscep t ible to a common mode fa i lure (e g , seismic e " eHt , +/-G-&& G..t: Horma l pm er , siHgle R-Yrn error ) . It is assumed , based on 1

engineering judgment , that while in MODES 4 and 5 , one ECCS injection/spray subsystem can b e manua l ly init i ated to maintain adequate reactor vessel water l evel .

As discuss e d in Re f e rences 1 , 2 , 3 , 4 , and 5 , ope rating experience has shown RPV water inventory to be significant to public health and safety . Therefore , RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50 . 36 (c ) (2 ) (ii ) .

Permissive and interlock setpoints are genera l l y considered as nominal values without regard to measurement accuracy .

The specific App l icable Safety Ana l yses , LCO , and Applicability discussions are listed below on a Function by Function basis .

(continued )

CLINTON B 3.3 - 122b Rev i s i on No . ~

0 (lJ >' (/) >' to t-< CJZ::i:>ro >'

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z ~ t-<t:rlt-< t:rl f-3 0 >' t-< f-3 H CJ) 0 0 'U (/) >--< 0 z CJ'Ut:rl rt t-< (/)

to f-J- H ~ t-<

CJ 0 t:rl c >' t-<

(]) to 0 Q. H 0 t-<

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HHiHHi H!1' It u~ ~1 f H

f-3 1

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CJ Jti df rf t' rt

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~ Ji P r t tru It {

id l i i ~ r t;f h f 0

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RPV Water Inventory Contro l I nstrumentat i on ,f--

B 3.3.5.2 BASES APPLICABLE ~ ~ Discharge HG-W = bGW Allo11able Ealtws a-re- R-i-gl+/-

SAFETY e nough -t-o- e nsur e -t-Ba-t- -t-Be- p-ump -t-1--Gw -ra-t-B -i-& suffici e nt .t-o-ANALYSES , LCO , prot e ct -t-Be- p-ump-,- ye-t, G-W e nough -t-o- e nsur e -t-Ba-t- -t-Be- closure and APPLICAB I LI TY G-.t: -t-Be- minim um -t-1--Gw ~ -i-& in it i at e g -t-o- .a,.1.J,..o.w. .f.u.l..l. -t-1--Gw (continued) .i.n.-t-o- -t-Be- ~

~ channel G-.t: .t.J:+/-. ~ Discharge ~ = bGW Fnnction -i-&

regnireGl -t-o- oo OPE1UB1E .if+ ll4GDE.£. 4 .a-00 ~ ~ -t-Be- associateGI

~ G-r ~ p-ump -i-& reguired -t-o- oo OPEP:AB1E b-y l,CQ. ~ .t-o-e nsur e -t-Be- -p-uHlp8- a--r-e- capabl e G-.t: inj e cting .i.n.-t-o- -t-Be- P: e actor Pr e ssur e Ee ss e l wH-e-H- manually initiat e g

.J-,...a....,.. P:eactor ~ Isolation Cooling (P:CIC) £torag e ~

~ = bGW bGW -l-e-v-e .if+ -t-Be- RC-+/--C £torag e +e-nk indicat e s -t-Be-una' railability G-.t: e.++ ag e quat e supply G-.t: mak e up ~ .f.r.Gfl'I

~ normal sourc e Mormally -t-Be- sldction " al " e s b e tu ee n

~ ~ -t-Be- RC-+/--C £ torage +e-nk a--r-e- ~ ~ ~ .f.G-r ~

injection ~ w .t.a.k.@.n, .f.r.Gfl'I .t.J:+/-. RC-+/--C £torage ~

Flo1 '9 er , .i.ct .t.AA ~ ~ .if+ ~ RC-+/--C £torage +e-nk ~

~ a- pr e s e lect e d l e u e l , .f-i-r-8-t- -t-Be- suppr e ssion pG-G suction ¥a-l-¥e- automatically op e ns , ~ -t-Be-n -t-Be- RC-+/--C £torage

~ sldction ¥a-l-¥e- automatically clos e s -'+/--R--i-.s- e nsur e s -t-Ba-t-e.++ ag e guat e supply 4.f: mak e up ~ -i-& a " ailabl e -t-o- -t-Be- ~

p.ldHlp-.- M pr e " e nt losing suction -t-o- -t-Be- p-ump-,- -t-Be- suction

" al " es ~ interlockeg ~ -t-Ba-t- .t.AA gnppression pG-G suction

~ ffi.U-.£.t. ~ ~ before .t.AA RC-+/--C £torag e +e-nk snction

~ automatically clo8 e 8 RC-+/--C £torage -'+/-'-a+l-k hB¥e-l- = bGW eignal8 a--r-B initi a ted -f-r-Gm. -t-wB

-l-e-v-e tranBmitter8 ~ ~ -i-& arranged .,s.u.G-fi, .t.f+.a.t. either tranem.itter .a.AA a88ociated ~ .c-a-n ~ -t-Be- 8uppre88ion pG-G 8Uction ~ -t-o- ~ .a.00 -t-Be- RC-+/--C £torage -'+/-'-a+l-k 8uction

~ -t-o- cloee

-'+/-'-AA RC-+/--C £torage +e-nk be-¥e-+/-- = bGW Function 7\llo' rabl e .\la-1-uB

-i-& B-i-g-A enough -t-o- ensure adeguate p-ump suction fIB.a-G wB-i-1-e wa-te-r -i-& be-i-ng -t-a-keH- .f.r.Gfl'I -t-Be- RC-+/--C £tor age -'+/-'-aFl-k-,...

~ channel8 G-.t: -t-Be- RG+/-G £torage -'+/-'-a+l-k hB¥e-l- = bGW Function a--r-B ~ requireGI -t-o- ~ OPEP:l\BlE wH-e-H- JWG£. -i-& required -t-o- ~

0.PEP:l\BlE -t-o- fulfill ffie requirementB 4.f: l,CO ~ 3 2 , ~ -i-&

align e g -t-o- -t-Be- RC-+/--C £torag e ~ ~ -t-Be- RC-+/--C £torage +e-nk wa-te-r -l-e-v-e -i-& f+O.t. Hithin -t-Be- li mit8 G-.t: .£R ~ 3 2 ~

(continued )

CLINTON B 3.3 - 122d Rev i s i on No . ~

RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES APPLICABLE ~ .J-.-.G-..- .fW.C£- ~ Diacharge l?r e aatire #.i-gR- (Bypaaa ) a-00 SAFETY .fW.C£- £ygt e m HB-W Ra--t-e = -hGW (Bypagg )

ANALYSES , LCO ,

and APPLICAB I LI TY ~ miI:1imt1m .f..l.g..w. i1:rntrt1m.e Hta &re- prg" ig e g w prgt e ct .t.AA (continued) .fW.C£- p.blmp .f.r.GHl g" e rh e atiHg :wfi.ef+ .t.AA p.blmp -i-& ope ratiHg a.H-G

.t.AA agggciat e g iHj e ctioH ~ -i-& ~ ~ ~ ~

mi Him ' m .f..l.g..w. ~ ~ -i-& op eH e g ~ J,..Q.w .f..l.g..w. a.H-G ~

1 p.blmp gigch:uge pre gg11re ~ a e i::ia e g , a.H-G .t.AA ~ -i-&

atitomatically cloaed ~ -t-00 .f..l.g..w. -r-a-ffi -i-& ade qtiate w prgt e ct .t.AA p.blmp G-r- -t-R-e- diacharg e pre aatir e -i-& J,..Q.w (iHdicatiHg .t.AA .fW.C£- p.blmp -i-& ~ gp e ratiHg )

GHe- .f..l.g..w. traHam.itt e r -i-& ~ w g e t e ct .t.AA ~ £ygt e m' g

.f..l.g..w. .r.a.t.-.- ~ ~ -i-& ;;i rraHge g ~ .t.J:J..e.t. .t.AA traHam.itter catia e a .t.AA miHim11m ~ ~ .t.Q. ~ prg u ig g g .t.AA .fW.CS p.blmp diacharg e preaatire , a e Haed fl-¥ aHgtJ:J.er traHamitt e r , -i-&

~ e Hgtigh ( iHdicatiHg .t.AA p.blmp -i-& ope ratiHg ) ~ ~

W-i-+/- ~ .t.AA miHimtim .f..l.g..w. ~ GR-Ge- .t.AA cloatire a e tpgiHt

-i-& e 2c c e e g e g ~ ~ W-i-+/- .a-1-&G ~ ~ .fW.C£- pbl-Hlp gigchaP3e pr e aatir e g e cr e aaiHg ~ -t-R-e- ge tpoiHt )

~ ~ £ygt e m. HB-W ~ = -hGW a.H-G ~ ~ Diach;;irge l?regg11re = #.i-gR- Allgo;;il?le ~ -i-& ~ eHongh w eHanre

.t.J:J..e.t. pbl-Hlp .f..l.g..w. -r-a-t.e -i-& atiffici e Ht w prot e ct -t-f+/-e. pt!-ffip-,- -'fe-l-J,..Q.w e ngtigh w e natir e .t.J:J..e.t. .t.AA cloaure G-f .t.AA m.inimum .f..l.g..w.

~ -i-& iHitiate d w e-l-1-Gw -f.bl-l .f..l.g..w. -i-H-t-9 .t.AA GG-re-.--

~ ~ ~ Diacharge l?r e ggnr e #.i-gR- Zl ll011ct1?l e ~ -i-&

.g.g.t. ~ 9H0 1gh w 9Ha ti rg .t.J:J..e.t. .t.AA ~ W-i-+/- ~

1 w ~

~ .t.fi..e. ~ -i-& ~ op e r;;itiHg GHe- channel G-f e-aBB- Functign -i-& required .t.G- Be- OJ?EgABLE wf+/-BB-

.fW.CS -i-& r e qtiir e d w Be- OJ?Eg?l £J LE fl-¥ bGG ~ -i-n ~ 4-

.a-00 .a.,..

(continued )

CLINTON B 3.3 - 122e Rev i s i on No . ~

RPV Water Inventory Contro l I nstrumentat i on B 3.3.5.2 BASES APPLICABLE RHR System Iso l ation SAFETY ANALYSES , LCO , 4--.-e- - Reactor Vessel Water Level - Low . Level 3 and APPLICAB I LI TY (continued) The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water l evel iso l ation instrumentation prior to the RPV water level being equa l to the TAF . The Reactor Vessel Water Level - Low , Level 3 Function is on l y required to be OPERABLE when automa t ic isolation of the associated RHR penetration f l ow path is credited in ca l culating DRAIN TIME .

Reactor Vessel Water Leve l - Low , Level 3 signals are initiated from four level transmitters (two per trip system) that sense the d i fference between the pressure due to a constant column of water (reference l eg ) and the pressure due to the actua l water level (variable leg ) in the vesse l.

While four channels (two channels per trip system ) of the Reactor Vessel Water Leve l - Low , Level 3 Function are available , only two channels (al l in the same trip system )

are required to be OPERAB LE .

The Reactor Vessel Water Level - Low , Level 3 Allowable Value was chosen to be the same as the RPS Reactor Vessel Water Level - Low , Leve l 3 Al l owable Value (LCO 3 . 3 . 1 . 1 ),

since the capabi l ity to cool the fue l may be threatened .

(continued )

CLINTON B 3.3 - 122f Rev i s i on No . ~

RPV Water Inventory Contro l I nstrumentation B 3.3.5.2 BASES APPLICABLE Reactor Water Clean u p (RWC U) System I solation SAFETY ANALYSES , LCO , ~ - Reactor Vessel Water level - Low Low , Level 2 and APPLICAB I LI TY (continued) The definition of DRAIN TI ME allows crediting t he closing of penetration flow paths that are capable of being automatically isolated by RPV water level isolation instrumentation prior to the RPV water leve l be i ng equal t o the TAF . The Reactor Vessel Water Level - Low Low , Level 2 Function associated with RWCU System isolation may be credited for automatic isolation of penetration f l ow paths associated with the RWCU System .

Reactor Vessel Water Leve l - Low Low , Leve l 2 i s initiated from two channels per trip system that sense the difference between the press u re due to a constan t column of water (reference leg ) and the pressure due to the actua l water level (variable l eg ) in the vessel . While four c h annels (t wo channels per trip system ) of the Reactor Vessel Water Level - Low , Level 2 Function are avai l able , on l y two channels (al l in the same trip system) are required to be OPERABLE .

The Reactor Vessel Water Level - Low Low , Leve l 2 Allowab l e Value was chosen to be the same as the ECCS Reactor Vessel Water Level - Low Low , Level 2 Al lowab l e Va l ue (LCO 3 . 3 . 5 . 1 ) , since the capabil i ty to cool the fue l may be threatened .

The Reactor Vessel Water Level - Low Low , Leve l 2 Function is on l y required t o be OPERABLE wh en automatic i sola t ion of the associated penetration flow path is credited in calcu l ating DRAIN TIME .

ACT I ONS A Note has been provided to modify the ACTIONS related to RPV Water Inventory Control instrumentation channels .

Section 1 . 3 , Completion Times , spec i fies t h at once a Condition has been entered , subsequent divisions ,

s u bsys tems , compone nts , or variables e xpr e ss e d i n the Condition discovered to be inoperab l e or not wi thin limits will not result i n separate entry into the Condi tion .

Section 1 . 3 also specifies that Requ i red Actions con t inue to apply for eac h additional failure , with Complet i on Times based on initia l entry into the Condi tion . However , t h e Required Actions for inoperable RPV Water Inventory Control instrumentation channels provide appropriate compensatory meas u res for separate inoperable Condi tion entry for each inoperable RPV Water Inventory Contro l instrumentation channel .

(continued )

CLINTON B 3.3 - 122g Rev i s i on No . ~

RPV Water Inventory Contro l I nstrumentation B 3.3.5.2 BASES ACTIONS (continued)

P: si;;p;iirs 8 AstiGH A-.-l- 8ir s -;=;tg ~ .i.fi.t.G. .:tJ:+e. apprgpriat s CeH8itieH r s f s r s H-;; e g ffi ~ ~ ~ 5 2 - 1 ~ appli-;;abl s Cm:i.8iti91:1 r e f e r e H-;; 0 8 ffi .:tJ:+e. ~ .i.& FttH-;=;tiGH 8 e p e H8 e Ht

~ ~ ~ ,;J:ieiHHQl .i..e. 8ieQ9" HQ8 iHGp@reiblg , CGH8itiGH A .i.&

eHts:rng .f.G+ .t.J:i.a.t; QA&lJ'.l.J'.l.91 ~ i;n*gu iggg .f.G+ tr;;i!'.l.gfgr w .t.00 apprgpriat e £ttbseqtt@Ht CGHditiGH

~~ ~

IA.1 . A.2.1. and A.2.2

" 2 1 , """ -+-

RHR System Iso l ation , Reactor Vesse l Water Leve l - Low Leve l 3 , and Reactor Water Cleanup System , Reactor Vessel Water Level - Low Low , Level 2 functions are applicable when automa t ic isolat i on of the associated penetrat i on f~ low path is credited in calc u lating Drain Time . If t h e A.1 instrumentation i s inoperable , Requ i red Action ~ irects immediate action to place t he channe l in trip . With the inoperable c h annel in the t ripped condition , t h e remaining channel will iso l ate the penetration f l ow path on low water A.2.1 If both channels are inoperable and p l aced in tr i p ,

flow path wi ll be isolated . Al terna t ive l y ,

1--~'-"+J..U..J;;,f;i"°"-_....(;..i;.-..c;~~..,.........,o--,E'e-6f'\:H:-lE'e-~ t h e associated pen et ration .-----.

f l ow path (s ) be i mmedia t ely declared incapable of IA.2.2 I a u toma t ic isolat i on . Re q uired Action ~ d irects initia t ing action to ca l culate DRAIN TIME . The calcu l ation cannot credit automatic isolation of the affected penetration flow path ( s ) . t" bG-W- reagtgr " 98891 pr988ttrs 8igHal8 a..r.e- ~ .a...s- psrmi88ius8

.f.G+ .:tfi.e. +/-G.w pr988t1T9 EG.C.£. iHj98ti9H/8pray 8t1B8]'8t9m H\3.Httal ir:iitiatiGH fttH-;=;tiGH8 U .t.f:i...i.& psrmi8eiue .i.& iHGperabls ,

maJ'.l.ttal iJ'.l.itiatiGJ'.l. &f. m .i.& prgfl.ibiteg Tl:lergfgrg , .:tJ:+e.

p e rmi88i " O Hltl--&t be- pla-;; g d ffi .:tJ:+e. -t-r-i-p QGHditiGH Pitl:iiH 00-tl-T-r W-i-t-R- .:tJ:+e. permi88i " e ffi .:tJ:+e. -t-r-i-p ggr:iditign , manttal iHiti a tiGH may- be- perfgrmed -P-r-i-G-r- -t-G- plaGiHg .:tJ:+e.

permi88iue ffi .:tJ:+e. tripped 89HditiGH 1 .:tJ:+e. epsr a tgr G-a-R .t.a.k-e maHttal 8GHtrgl &f. .:tJ:+e. ~ ~ .:tJ:+e. iHj98ti9H ~ -t-G- iHj98t

~ .i.fi.t.G. .:tJ:+e. R-.J2-',l..,...

~ Cgmpl e tiGH .T.Htte- G-f. ~ .i.& iHt s H8 e 8 -t-G- .a-1--1-G.w .:tJ:+e.

gper a tgr ~ -t-G- O" alttate .a.fi..lf 8i8QG" ere8 iHGperabilitie8 ~

-t-G- ~ .:tJ:+e. -;=; J:i a HHe l ffi .t.r.i.p...-

(continu ed )

CLINTON B 3.3 - 122h Rev i s i on No . ~

RPV Water Inventory Contro l I nstrumentation .+---

B 3.3.5.2 BASES ACTIONS (continued) gequired Actiona -Id-.--+/- aH-G ~ ~ intended w enaure Wa-t-appropriate actiona a.re- ~ .i.f. multiple , inoperal2le cH.annela PitH.in -t.H-e- &aHte- Function reault .i..n .a .J,..g..g..g. G-f-a tt tom at i c 8 u c ti on .,g.w..ap ~ -t.H-e- ~ 8'/ 8 t em .f.r-OHl -t.H-e- RG.J.G ator;;igg .t.a.+/-+k w .t.J+g anpprgggion ~ ~ ~ gygtgm ~

oo GleclareGl iAopenele uiUi.iA .1. 00.u+/- G+ -t.H-e- ~ p.ump attction ~ oo aligned w -t-00 attppreaaion -pGG-1-., aince , .i.f.

aligned , -t.H-e- function -i-.s- already performed

-'+/-'-Re- .1. OOtJ.r. CompletioA Um -i-.s- acceptal2le 12ecatt8e .i..:t; minimizeg -t.H-e- .r.i..g..J.;, G-f- ~ ~ nee9e9 Pitfiout .a..i:+ a9eqttate

~ aonrcg w.fi.i.l.g. allouiAg .t.i.m ~ r@atoratioA G+

iligAmeAt G-f- ~ p.ump attctioA w -t.H-e- attppreaaioA ~

U .a..i:+ ~ G+ ~ Qigcf:i.arge ~ = W.w. 12ypa88 function G-.r.

~ £ygtem Qigcf:i.arge Preaaure = filgl+/- G+ ~ ~ = W.w.

12 yp a 8 8 f n Act i o A -i-.s- i Ao pg r a 12 lg , -t-00.r.- -i-.s- .a .;r.i..a.k -t-fi.a-t- ~

a88ociate9 ~ p.ump ~ o" QrHeat ~ .:t.AA p.ump -i-.s-operating aH-G -t.H-e- aaaociated injection .v-a-l¥e- -i-.s- fi.G.-t- -f-tt-l-1-y-Gpe-fi.-- -+/--H- tJi...i-& condition , -t.H-e- operator -Ga-H- -t-a-k-e manttal control G-f- -t.H-e- p.ump aH-G -t.H-e- injection .v-a-l¥e- w enattre -t.H-e-p.ump ~ fi.G.-t- o" erH.eat

~ .:f-4 OOtJ.r. Compl@tion ~ .w..a.a. cfioggn w ~ .t.i.m ~ -t-00 op>Hator w e " alnate aH-G repair .a.f+¥ 9iaCO" >He9 inoperal2ilitiea p-r-i-o-r w declaring -t.H-e- affected 8t1BByBtem inoperable. -'+/-'-Re- Completion Um+/--& appropriate g-i-¥BB- -t.H-e-ability w manually &t-a-r-t- -t.H-e- ~ pttmp..s- -a-00 GpB-R -t.H-e-inj ection ualueg .a.& neceBBary w enBure -t.H-e- affer;:;ted p.uHlf' OOe..s- fi.G.-t- ou er!::i.eat W-i-t-R -t.H-e- geqttired Ar;:;tion a-BG aBBOGiated Completion Um G-f-ConditionB G, If., G+ E fi.G.-t- me-t,- -t.H-e- aBBOGiated ~

injer;:;tion/Bpray BttbByBtem ma.:r be inGapable G-f- performing -t.H-e-intended fttnGtion , a-BG ~ be der;:;lared inoperable immediately (co n tinued )

CLINTON B 3.3 - 122i Rev i sion No . ~

RPV Water Inventory Control Instrumentation B 3.3.5.2 BASES (continued) The following SRs apply to SURVEILLANCE As ~ .H+ -t-00 beginning &t: -t-00 $R.&-r -t-00 SR-& .f.G-+/-' each RPV REQUIREMENTS Water Inventory Control instrument Function -a£-B ~ in -t-fi.B SR-& column &t: Table 3 . 3. 5 .2 - 1 .

SR 3.3.5.2.l Performance of the CHANNEL CHECK ensures that a gross failure of instrumentation has not occurred . A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels . It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value .

Signifi c ant deviations between the instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious . A CHANNEL CHECK guarantees that undetected outright channel failure is limited; thus , it is key to verifying the instrumentation continues to operate properly between each CHANNEL FUNCTIONAL TEST .

Agreement criteria are determined by the plant staff , based on a combination of the channel instrument uncertain t ies ,

including indication and readability . If a channel is outside the criteria , it may be an indication that the instrument has drifted outside its limit .

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

The CHANNEL CHECK supplements less formal , but more frequent , checks of channels during normal operational use of the displays associated with the channels required by the LCO .

(continued)

CLINTON B 3.3 - 122j Revision No . ~

Primary Containment and Drywell Isolation Instrumentation B 3.3.6.1 BASES ACTIONS K .1 and K. 2 (continued)

If the channel is not restored to OPERABLE status or placed in trip , or any Required Action of Condition I or J is not met and the associated Completion Time has expired , the plant must be placed in a MODE or other specified condition in which the LCO does not apply . This is done by placing the p l ant in at l east MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times are reasonable , based on operating experience , to reach t he required plant conditions from full power conditions in an order l y manner and without challenging plant systems .

L . 1 and L . 2 If the channel is not restored to OPERABLE status wi t hin the allowed Completion Time , the associated SLC subsystem(s) is declared inoperable or the RWCU System is isolated . Since this Function is required to ensure that t he SLC System performs its intended function , sufficient remedial measures are provided by declaring the associated SLC subsystem inoperable or isolating the RWCU System .

The Completion Time of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is acceptable because it minimizes risk while allowing sufficient time for personnel to isolate the RWCU System . RWCU isolation is achieved by closing 1G33F001 or 1G33F004 , which are the containment isolation valves associated with this isolation function .

M. l r M-.-2-,- M J 1 , M J 2 , M J J , a-AG~

If the channel is not restored to OPERABLE status or placed in trip within the allowed Completion Time , the associated penetration flow path should be isolated (i . e ., closing either 1El2 - F008 or 1El2 - F009) . However , if the shutdown cooling function is needed to provide core cooling , these Required Actions allow the penetration flow path to remain uniso l ated provided action is immediately initiated t o restore the channel to OPERABLE status G-F w firo u ide ffie.a+l ~ Gontrol G-f. flOtential radioaGti u e releases . ~

inGhades enstuin~ seGondary Gontainment .i...s- Ol?Kl~~Al3I.:e;:: ; .a.t.

e-a-&t- G-H-e- £ t::rn sH> y Ga-& Tr e a tm en t +£.G.T+. s yg s y s t em .i...s- 0 pg g 71 13 I.E ;

.a.AG seGoAGla:ry GoAtaii:imeflt isolatioi:i Gafla9ility (i e , .a.t.

e-a-&t- G-H-e- isolation ¥a-l¥e- a-AG assoGiated inst:rt1mentation -a--:r-e OJ?Eg7\J3I,E G-F ~ aGGeflta9le 21slmii:iist:r21ti u e GoAt:rols w 21ssn:re isol21tioi:i Gafla9ility ) .i-1:+ ~ seGoAGla:ry Goi:it21ii:imei:it a-AG seGondary Gontainmeflt 9yflass fJenetration ~ ~ ~

isolated tJ+a.t. .i...s- asst1med .t.G .9e isolated .t.G miti~ate (co n tinued )

CLINTON B 3 . 3 - 168 Rev i sion No . +/--G.=4

Pr i mary Conta i nment and Drywe l l Iso l ation I nstrumentat i on B 3.3.6.1 BASES ACTIONS M. l , M-.--6, M J 1 , M J 2 , M J J , .a-AG M-.--J-.-4 (cont i nued )

radioacti u ity r e l e a£ e £ Tu-i ~ Pe- p e rforme d aS- a+/-+

admiI:1i2trati" e cJ::J. e ck , b¥ e xaminiI:1g ~ ~ ~

information , w d e t e rmiA e .i..f. ~ compone nt£ .a.r.e .g.y..j; Q..f ge p ric e ~ maint e nanc e ~ ~ r e a£On£ .J.t. .;i,..a. fl4t.

ngcggg:;iry w pgrform .t.J::J..- £HP ' 9ill:;incgg nggdgd w dgmon2tr:;itg

.t.00 0PE1U'1H1.ITY Q..f .t.00 Gompon0i:i.tg .r..f.,.. J::J.o\'G" Gr , d-Wf r e quir e d Gompoi:i. e i:i.t .;i,..a. iAop e rabl e , -tRe-A -i-t- m-&t- Pe- r e 2tore d w QpEg 71 ~.bE 2tatu£ .I-fl- .t.fl..i-& Ga-&e-r ~ £uP ' e illanc e £ ~

Aee4 w Pe- p e rform e d w r e 2tore ~ Gompon e nt w QPEg 11 ~1.E gtatug Ii:i. additioi:i. , .a..t. J,..e..a.,s..t. ' ~ .i.f+ ~ ~

Goi:i.taii:i.m e nt p e raoi:i.n e l .a.i+/-. ~ m-&t- Pe- Gloa e d ~ c l oa e d

.a.i+/-. ~ Q.Q..g.r. Gomplgtgg .t.J::J..- boHi:i.dary ~ coi:i.trol Q..f potGi:i.ti:;il radioaGti" G rglg:;iggg W.i.tJl. .t.00 appropri:;itg admii:i.iatrati" e Gontrol£ J::\oPe " er , -tR-e Gloa e d Q.Q..g.r. &a-1:+ ~

ope n e d int e rmitt e ntly ~ ~ .a-AG ~ Tu-i allouanc e .;i,..a.

acG e ptabl e 4u-e- w ~ Aee4 ~ Gontainm e nt aGC e ££ .a-AG 4u-e- w

~ ~ progr e ££ioi:i. Q..f e u e nt£ ~ ~ r e ault ~ .a.

r e aGtor " e ££ e l draii:i.douA e " e i:i.t g e actor " e ££ e l draindoPn e " e nt£ ~ fl4t. Pe- e xp e Gt e d w r e n;i l t .i.f+ ~ imm e diat e rglg:;igg G-f appr9Giablg fi££ion prodnGt£ w .t.J::J..- Goi:i.t:;iinmgi:i.t

itmoapJ: :J.grg Act i ons must continue unti l;f\.a..l.l. rgq11irgmgi:i.t£ Q..f

.tR--i Condition .a.r.e £ati2fi e d I the channel is restored to N. l , N. 2 . 1 , and N. 2 . 2 OPERABLE status.

If the channel is not restored to OPERABLE status or placed in trip within the allowed Comp letion Time , the associated penetration flow path ( s ) shou l d be iso l ated (Required Action N. l ) . I solating the affected penetration flow path (s ) accomp l ishes the safety function of the inoperable instrumentation . Alternately , the p l ant must be placed in a condition in which the LCO does not apply . If a p plicable ,

movement of recent l y irradiated fuel assemblies (i . e ., fuel that has occupied part of a critical reactor core wi t hin t he previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) must be i mmediate l y suspended .

Suspension of these activit i es shal l not preclude complet i on of movement of a component to a safe condition .

(continued )

CLINTON B 3 . 3 - 1 69 Rev i s i on No . G.=2-

LOP Instrumentation B 3.3.8.1 BASES APPLICABLE l . a , l. b , 2 . a , 2.b . 4 .1 6 kV Emergency Bus Undervoltage SAFETY ANALYSES , (Loss of Voltage) (continued)

LCO , and APPLICABILITY The Division 3 4 . 16 kV Emergency Bus Loss of Voltage Function 120 - volt Basis trip setpoint is ~ 67 volts and ~ 78 volts .

Six channels of 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) Function per associated emergency bus for Divisions 1 and 2 and four channels for Division 3 are only required to be OPERABLE when the associated DG is required to be OPERABLE to ensure that no single instrument failure can preclude the DG function . (Six channels input to each of the Division 1 and Division 2 DGs and four channels input to the Division 3 DG . Each of the six channels for Division 1 and six channels for Division 2 is an inverse time delay relay. Each of these time delays are considered to be separate channels . For Div i sion 3 , the Loss of Voltage Function logic inputs to a single time delay relay . Thus ,

only one time de l ay channel is associated with Division 3 . )

Refer to LCO 3 . 8 . 1 , "AC Sources-Operating, " ~ J.GG J g ~ '

.!.!.AG £9H:rggg £l:J.Ht.bl9HA 1 " for Applicabi li ty Bases for the DGs .

l . c , l. d , l . e , 2.c , 2 . d , 2 . e . 4 . 16 kV Emergency Bus Undervoltage (Degraded Voltage )

A reduced voltage condition on a 4.16 kV emergency bus indicates that while offsite power may no t be completely lost to the respective emergency bus , power may be insuffi c ient for starting large motors without riski n g damage to the motors that could disab l e the ECCS function.

Therefore , power supply to the bus is transferred from offsite power to onsite DG power when the voltage on the bus drops below the Degraded Voltage Function Allowable Values (degraded voltage with a time delay ). This ensures that adequate power will be available to the required equipment .

Th e Bus Unde rvoltag e Al l owabl e Va lu e s ar e low e nough to prevent inadvertent power supply transfer , but high enough to ensure that sufficient power is available to the required equipment . As stated above , the purpose of this instrumentation i s to ensure that sufficient power will be available to support the ECCS function du rin g a LOCA .

During a LOCA , the ECCS and other safety systems will be initiated at the start of the event . This l arge loading of the safety buses results in a voltage transient of (co n tinued )

CLINTON B 3 . 3 - 225 Revision No. 4=J.

LOP Instrumentat i on B 3.3.8.1 BASES ACTIONS B .1 (continued)

If any Required Action and associated Completion Time is not met , the associated Function may not be capab l e of performing the intended function . Therefore , the associated DG (s ) are declared inoperable immediately . This requires entry into app li cable Conditions and Required Actions of LCO 3 . 8 . l ~ l.CO] S l , which provide appropriate actions for the inoperab l e DG ( s ).

SURVEILLANCE As noted at the beginning of the SRs , the SRs for each LOP REQUIREMENTS Instrumentation Function are l ocated in the SRs column of Table 3 . 3 . 8 .1-1.

The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances , en t ry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided the associated Function maintains DG initiation capab ili ty . Upon complet i on of the Surveillance ,

or expiration of the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months allowance , the channel must be returned to OPERABLE status or the app l icab l e Condition entered and Required Actions taken .

SR 3 . 3 . 8 . 1. 1 This SR has been deleted .

SR 3 . 3 . 8 . 1. 2 A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function . For series Functions , i . e ., for the degraded voltage relays in series with their associa t ed delay timers , a separate CHANNEL FUNCTIONAL TEST is n ot required for each Fu nction , provided each Function is tested . A successfu l test of the required contact (s) of a channel relay may be performed by the verification of the change of state of a sing l e contact of the relay . Th is c l arifies what is an acceptable CHANNEL FUNCT I ONAL TEST of a relay . This is acceptable because al l of the other required contacts of the relay are verified by other Technical Specifications and non - Technical Specifications tests at least once per refueling interval with applicable extensions .

Any setpoint adjustment shall be consistent with the assumptions of the current plant specific setpoint methodology .

The Surveillance Frequency is control l ed under the Surveillance Frequ ency Control Program .

(co n tinued)

CLINTON B 3 . 3 - 228 Rev i sion No . -+/-4=6

LOP Instrumentat i on B 3.3.8.1 BASES SURVEILLANCE SR 3. 3 . 8 . 1. 3 REQUIREMENTS (continued) A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor . This test verifies the channel responds to the measured parameter within the necessary range and accuracy . CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations consistent with the plant specific setpoint methodology.

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

SR 3 . 3 . 8 . 1. 4 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required actuation logic for a specific channel . The system functional testing performed in LCO 3 . 8.1 e+l-4 J,,G.Q ~ overlaps this Surveil l ance to provide comp l ete testing of the assumed safety functions .

The Surveillance Frequency is contro ll ed under the Surveillance Frequency Control Program .

REFERENCES 1. USAR , Section 8 . 3 . 1.1. 2 .

2. USAR , Section 5 . 2 . 2 .

3. USAR , Section 6 . 3 . 3 .

4. USAR , Chapter 15 .

5. I P Calculat i on 19 - AN - 1 9 .

CLINTON B 3 . 3 - 229 Rev i sion No . -+/-4=6

RPV Water Inventory Contro l B 3.5.2 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS ), REACTOR PRESSURE VESSEL (RPV )

WATER INVENTORY CONTROL , AND REACTOR CORE ISOLATION COOLING (RCIC )

SYS TEM B 3.5.2 RPV Water I nventory Control BASES BACKGROUND The RPV co n tains penetrations be l ow t h e top o f the active fuel (TAF ) t h at have the potential to drain the reac t or coo l an t inventory to be l ow the TAF . If the water leve l should drop be l ow the TAF , the ability to remove decay heat is reduced , wh ich could lead to elevated cladding temperatures and c l ad perforation . Safety Limit 2 . 1 . l . 3 requires the RPV water l evel to be above the top of t he active irradiated f u el at all times to prevent such eleva t ed cladding temperatures .

APPLICAB LE With t h e unit in MODE 4 or 5 , RPV water inventory contro l is SAFETY ANALYS ES not required to mitigate any events or accidents eva l uated in the safety analyses . RPV water inventory control is required in MO DE S 4 and 5 to protect Safety Limit 2 . 1 . 1 . 3 and the fuel c l adding barrier to prevent the re l ease of radioactive material to the environment should an unexpected draining event occur .

!considered ID gg n b l e ended qui:l,lotine break of the Reactor Coolant System (RCS ) is no~ p98ttt l atgg in MODES 4 and 5 due t o the reduced RCS pressure , reduced piping stresses , and ducti l e

....-~~~~~~~~- piping systems . Instead , an event is considered in which an event that creates singlg gpgratgr m G-r- in i tiating event a l lows draining of the RPV water inventory through a sing l e penetration flow a drain path through path with the highest f l ow rate , or the sum of the drain multiple vessel rates throu h mu l ti le enetration f l ow a h suscep t ible to penetrations located a common mode fa i lure ( ~ sgismi8 g u gnt , loss of normal power , single human error ) . It is assumed , based on below top of active engin ring judgment , that while in MO DES 4 and 5 , o n e l ow fuel , such as pr e ssu e ECCS injection/spray subsyst e m can maintain adequa e reactor vessel water level .

or As discussed in References 1 , 2 , 3 , 4, and 5 , operating experience has shown RPV water inventory to be significant to public h ealth and safety . Therefore , RPV Water Inventory Control satisfies Criterion 4 of 10 CFR 50 . 36 ( c ) (2 ) (ii ).

LCO The RPV water l eve l mu st be controlled in MODES 4 and 5 to ensure that if an unexpected draining event should occur ,

the reactor coolant water level rema i ns above the top of t he active irradiated f u el as required by Safety Limit 2 . 1 . 1 . 3 .

The Limiting Condition for Operation (LCO ) requires t he DRAIN TIME of RPV water inventory to the TAF to be ~ 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A DRAIN TIME of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months is considered reasonable to (co n tinued )

CLINTON B 3 . 5 - 17 Revis i on No . ~

RPV Water Inventory Contro l B 3.5.2 BASES LCO identify and initiate action to mitigate unexpected draining (continued} of reactor coo l ant . An event that cou l d cause l oss of RPV water inventory and result in the RPV water level reaching the TAF in greater than 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months does not represent a significant chal l enge to Safety Limi t 2 . 1 . 1 . 3 and can be

.--~~~~~~ managed as part of normal plant operation .

aligned and from the control room One ECCS injection/spray subsystem is equire OPERABLE and capab l e of being manually started to provide defense - in - depth should an unexpected draining event occur .

OPERABILITY of the n ECCS injection/spray subsystem is defined as either one ECCS injection/spray of the three Low Pressure Coo l ant Injection (L PCI }

subsystem includes subsystems , one Low Pressure Core Spray (L PCS } System , or one High Pressure Core Spray (HPCS } System . The LPCI any necessary valves, s u bsys t em and the LPCS Sys t em cons i st of one moto r d ri ven instrumentation, or pump , piping , and valves to transfer water from the controls needed to suppression pool to the reactor press u re vessel (RPV ) . The HPCS System cons i sts of one motor dr i ven pump , piping , and manually align and valves to transfer water from the suppression poo l or RC I C start the subsystem storage tank to the RPV . Management o f gas voids is from the control room. important to ECCS injection/spray subsystem OPERABI LITY .

The LCO is modif i ed by a Note t h at al l ows a LPCI subsystem to be inoperab l e during a l ignment and operation for decay heat removal with reactor steam dome pressure less than t h e residual heat removal cut - i n permissive pressure. Th is is necessary since the RHR system is requ ired to operate in the shutdown coo l ing mode to remove decay heat and sensible hea t from the reactor , and manual realignment from the shutdown coo li ng mode to t h e LPC I mode cou l d r esu l t i n p ump cavitation and voiding in the suction piping , resulting in the potentia l to damage the RHR system , inc l uding wa t er hammer . One LPC I s u bsystem is a l lowed to be considered inoperable for this tempora r y p eriod , because in s h u t down cooling mode it i s fu l fil l i ng a decay heat remova l capaci t y f u nction . At these low pressures and decay h eat levels , a reduced comp l e ment of ECCS s u bsystems should provide the required core cooling , thereb y a l low i ng operation of RHR shutdown coo l ing when necessary . Becau se of the restrictions on DRAIN TI ME , sufficient time wil l be available fo l low i ng an unexpected dra i ning even t to manua l ly align and operate t h e re q uired LPCI subsystem to mai n tain RPV wa t er inventory prior t o the RPV water l eve l reach ing the TAF .

(co n tinued }

CLINTON B 3 . 5 - 18 Revis i on No . ~

RPV Water Inventory Contro l B 3.5.2 "Instrumentation,"

BASES (continued )

APPLICABILITY RPV water inventory control is quired in MO DES 4 and 5 .

Requirements on water inventory ntro l in other MODES are "ECCS, RPV Water r-~cf'7;o~n~t~a~i=.;n:;-e~d~;;i.;;n-;--;L;C;..0:....s;__~

i:>...n Section 3 . 3 , Inetr1,1mgntat.ign , and other LCOs in ::>ection ._) . ,,, EC.CS.,.- ~ .a.n.Q ~ ~ I n u gntgry Inventory Control, Cgntrgl RPV water inventory contro l is required to protect and RCIC System." Safety Limit 2 . 1 . 1. 3 which is applicab l e whenever irradiated fuel is in t h e reactor vessel .

ACTIONS A . 1 and B . 1 If the required ECCS inject i on/spray subsystem i s inoperable , it must be res t ored to OPERABLE status within 4 h ours . In this Condition , t h e LCO controls on DRAIN TI ME minimize the possibility that an unexpected dra i ning even t could necessitate the use of the ECCS injection/spray subsystem , however the defense - in - depth provided by the ECCS injection/spray subsystem is lost . The 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Completion Time for restoring the requ i red ECCS i njection/spray subsys t em to OPERABLE status is based on engineering judgment that considers the LCO controls on DRAIN TIME and the low probabil i ty of a an unexpected draining even t that would result in a l oss of RPV water i nventory .

If the inop erable ECCS injection/spray subsystem is not restored to OPERAB LE status within the required Completion Time , action must be initiated immed i ately to establis h a method of water i njection capab le of operating without offsite electrical power . The method of water injection includes the necessary ins t r umentation and contro l s , water sources , and pumps and va l ves needed to add water to the RPV or refueli n g cav i ty should an unexpected draining event occur . The method of water injection may be manually operated and may consist of one or more systems or s u bsys t ems , and mu st be able to access water inventory capab l e of maintaining the RPV water level above the TAF for

~ 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . If recircu l ation of injected water would occur ,

i t may be credited in determining the necessary water volume .

(continued )

CLINTON B 3 . 5 - 19 Revis i on No . ~

RPV Water Inventory Control B 3.5.2 BASES ACTIONS 0 . 1 , 0 . 2 , 0 . 3 , and 0 . 4 (continued) operated and may consist of one or more additional method of water injection must be able to access water inventory capable of being injected to maintain the RPV water level above the TAF for ~ 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The additional method of water injection and the ECCS injection/spray subsystem may share all or part of the same water sources . If recirculation of injected water would occur , it may be credited in determining the required water volume .

Should a draining event lower the reactor coolant level to below the TAF , there is potential for damage to the reactor fuel cladding and release of radioactive material.

Additional actions are taken to ensure that rad i oactive material will be contained , diluted , and processed prior to being released to the environment .

The secondary containment provides a control volume into which fission products can be contained , diluted , and processed prior to release to the environment. Required Action D. 2 requires that actions be immediately initiated to establish the secondary containment boundary . With t he secondary containment boundary established , one SGT subsystem is capable of maintaining a negative pressure in the secondary containment with respect to the environment.

The secondary containment penetratio automatically Or secondary containment boundary . Req requires that actions be immediately i nitiated to verify that each secondary containment pen ation flow pat h is isolated or to verify that it can be manually isolated from the control room. Examples of manual isolation from the control room cou l d include the use of manual isolation pushbuttons , control switches , or placing a sufficient number of radiation monitor channels in trip . A secondary containment penetration flow path can be considered isolated Required Actions D.2, when one barrier in the flow path is in place. Examples of D .3, and D.4 are suitable barriers include , but are not limited to , a closed considered to be met secondary containment isolation damper (SCIO) , a closed manual valve , a blind flange , or another sealing device that when secondary sufficiently seals the penetration flow path . The primary containment, containment upper personnel airlock and other primary secondary containment containment penetrations that bypass secondary containment penetrations, and the are considered part of the secondary containment boundary ;

therefore , they must be considered when completing this Standby Gas Treatment action .

System are OPERABLE in One SGT subsystem is capable of maintaining the secondary accordance with containment at a negative pressure with respect to the environment and filter gaseous releases . Required Action LCO 3.6.4.1, LCO 0 . 4 requires that actions be immediately initiated to verify 3.6.4.2 , and LCO that at least one SGT subsystem is capable of being placed 3.6.4.3. in operation . The required verification is an administrative activity and does not require manipulation or testing of equipment .

(co ntinued )

CLINTON B 3 . 5 - 22 Revision No . G-=6

RPV Wate r Inventory Control B 3.5.2 BASES AC TIONS E.1 (continued}

If the Required Actions and associated Completion times of Conditions C or D are not met or if the DRAIN TIME is less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , actions must be initiated immediately to restore the DRAIN TIME to 2 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . In this condi t ion ,

there may be insufficient time to respond to an unexpected draining event to prevent the RPV water inventory from reaching the TAF. Note that Required Actions D. 1 , D. 2 , D.3 ,

and D.4 are also applicable when DRAIN TIME is less t han 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

SURVEILLANCE SR 3. 5 .2 . 1 REQUIREMENTS This Surveillance verifies that the DRAIN TIME of RPV water inventory to the TAF is 2 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The period of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months is considered reasonable to identify and initiate ac t ion to mitigate draining of reactor coolant . Loss of RPV water inventory that would result in the RPV wa t er level reaching the TAF in greater than 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months does not represent a significant challenge to Safety Limit 2 . 1 . 1 . 3 and can be managed as part of normal plant operation .

The definition of DRAIN TIME states that realistic cross -

sectional areas and drain rates are used in the calculation .

A realistic drain rate may be determined using a single ,

s t ep - wise , or integrated calculation considering the changing RPV water level during a draining event . For a Control Rod RPV penetration flow path with the Control Rod Drive Mechanism removed and not replaced with a blan k flange , the realistic cross - sectional area is based on the control rod blade seated in the control rod guide tube. If the control rod blade will be raised from the penetration to adjust or verify seating of the blade , the exposed cross -

sectional area of the RPV penetration flow path is used .

The definition of DRAIN TIME excludes from the calculation those penetration flow paths connected to an intact closed closed and system , or isolated by manual or automatic valves that are administratively lggJrnd , sealed , e.+/-:- gtJ::ierFise semued -i+l- .tfi.e Gl esed i;w sit i eH ,

controlled blank flanges , or other devices that prevent flow of reactor coolant through the penetration flow paths . A blank flange or other bolted device must be connected with a sufficient number of bolts to prevent draining -i+l- .tfi.e ~ ~ e.++

OperatiHg E-a-&i-& Earthg+iake . Normal or expected leakage from closed systems or past isolation devices is permitted .

Determination that a system is intact and closed or isolated must consider the status of branch lines .a.HG eHgeiHg p-l.a.H.t.

ma iHt eH3. H8 e.a.HG t es tiH g a Gti uiti es .

The Residual Heat Removal (RHR} Shutdown Cooling Sys t em is only considered an intact closed system when misalignment (continued}

CLINTON B 3 . 5 - 23 Rev i sion No . ~

RPV Water Inventory Control B 3.5.2 BASES SURVEILLANCE SR 3.5 . 2 . 1 (continued)

REQUIREMENTS issues (Reference 6) have been precluded by functional valve inter l ocks or by isola * *

n of RPV water out of an RH path, Or multiple penetration flow RHR Shutdown Cooling s paths susceptible to a common closed system if its c mode failure, to Remote Shutdown , which .___ _ _ _ _ _ __,_ _ _ _ _ _ _ __. tion signals . ~

temporary alterations in ~- ~

The exclusion of penetration f l w ~ from the j.......J::ie.t..e..r:ri:LJ....I:i..a.!~*~ 9 n of DRAIN TIME consider the pgtgntial support of maintenance effects m .Q+/- initiating ~ .Q.f:l.

....--.!::::::==========~ -i-t.em.& guppgrting maint e n:rnc e a.00 t e gting (rigg ing ,

If reasonable controls are scaffolding , temporary shielding , p i ping plugs , gnubb e r implemented to prevent r u failu re G-f. such .i-t.em&

,____ _ _ _ _ _ _ _ _ _ _____, ~ r e ettlt ~ a draining event from a closed system or between the RPV and the isolation device ,

temporary pgngtratign .f..l.g.w p.a..t.A ~ f:l..9.t. w gxcl g;lgg ~ ~ 1 alterations from ~ calc11latign .

causing Surveillance Requirement 3 . 0 . 1 requires SRs to be m between performances . Therefore , any changes in pl the effect of the temporary conditions that would change the DRAIN TIME require alterations on DRAIN TIME new DRAIN TIME be determined .

need not be considered.

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

include, but are not limited to controls consistent with SR 3 . 5 . 2 . 2 and SR 3 . 5 . 2 . 3 the guidance in NUMARC 93-01, "Industry Guideline The minimum water level of 12 ft 8 inches required or the suppression pool is periodically verified to ensure that the for Monitoring the suppression pool will provide adequate net positive suction Effectiveness of head (NPSH) for the ECCS pump , recirculation volume , and Maintenance at Nuclear vortex prevention . With the suppression pool water level less than the required limit, the required ECCS Power Plants," Revision4, injection/spray subsystem is inoperable unless it is aligned N UMARC 91-06, to an OPERABLE RCIC storage tank.

"Guidelines for Industry With regard to suppression pool water level values obtained Actions to Assess pursuant to this SR , as read from plant indicat i on Shutdown Management," or instrumentation , t he specified limit is not considered to be a nominal va lu e with respect to instrument uncertainties.

commitments to This requires additional margin to be added to the limit to NUREG-0612, "Control of compensate for instrument uncertainties , for implementation Heavy Loads at Nuclear in the associated plant procedures (Ref. 2).

Power Plants." When the suppression pool level is < 1 2 f t 8 inches , the HPCS System is considered OPERABLE only if it can take suction from the RCIC storage tank and the RCIC storage tank (co n tinued)

CLINTON B 3 . 5 - 24 Rev i sion No . ~

AC Sources - Shu tdown B 3.8.2 the ability to BASES manually start a LCO e l ectrical power s u pport , assuming a loss of the o fsite (continued ) circui t . Simi l arly , when the high pressure core s ray (HPCS ) is required to be OPERABLE , a separate offs ' te circui t to the Di vision 3 Class lE onsite electr i c l power distribution subsystem , or an OPERABLE Division 3 G, ensure an add i t i ona l sou r ce o f powe r f o r the HPCS . Toget e r ,

OPERABI L ITY of the required offsite c i rcuit (s ) an DG (s )

ll.5e::..!n.!s~u~res:.:::Su---:;:)'il" 9 Aatt:r 9 the availability o f s u fficient AC sources to operate the p l ant in a safe manner and to mitigate the consequences of pos t ulated events during shutdown (e . g ., fue l handling accidents ) .

The qualified offsite circu i t ( s ) must be capable of maintaining rated frequency and vo l tage whi l e connec t ed to their respective ESF bus (es ) , and accepting required loads during an acciden t. Qualif i ed offsite circuits are t h ose that are described in the USAR and are part of t he licens i ng basis for the plant . The offsite circuit consists of incoming breaker and disconnect to the respective reserve auxiliary transformer (RAT) or emergency reserve auxiliary t r ans f o r mer (ERAT ) , and the respect i ve c ir cu i t pat h including feeder breakers t o all 4 . 16 kV ESF buses required by LCO 3 . 8 . 10 . I n addition , an onsite , permanent l y insta l led static VAR compensator (SVC ) is availab l e for connec t ion to the offsite c i rcuits to s u pport required vol t age for t h e ESF b u sses . Connect i on of the SVC to the offsite circuit i s via circuit breakers to t h e secondary side of the RAT and/or ERAT .

Connec t ion and operation of the SVC ( s ) is dictated by the existing need for voltage sup port of t he offsite electrical power source ( s ) based on prevailing grid conditions . Thus ,

OPERABILITY of the offsite electrica l power source (s ) is norma l ly supported by , but i s not necessari l y dependent on ,

connection and operation of the SVC ( s ). Th e resu l tant i mpact on OPERABI LI TY of t h e offs i te e l ect ri ca l sou r ce (s )

from disconnecting the SVC (s ) from the offsite circuit (s )

can be determined by analysis b ased on u se of an established model of the o f fsite transm i ssion network and existing grid conditions , including availabl e generating sources , which can be u p dated on a dai l y or more frequen t bas i s . The mode l provides the capability to predict or determine what the onsite voltages would be at the RAT and/or ERAT (while connected to the offsite electrical sources ) under maximum postu l ated load conditions .

(co n tinued )

CLINTON B 3 . 8- 35 Rev i sion No . ~

AC Sources~Shutdown B 3.8.2 being manually BASES started LCO The required DG mu st be capable of etartiHg , accelerating to (continued ) rated speed and vo l tage , and connect i ng to its respective ESF bus ~ 9ete,-;ti9H Q..f. ~ tiA90P ' 91Lige , and accepting required loads. ~ 2:Qr;;_{PQAQQ ffit.1-8-t- b. :;i,-;,-;gmp l igl:J.gg Hitl:l. i H

-+/-- 2:8Q9Hda EaGR- JdG ffit.1-8-t- a-l-8-G- be- ,-;apablg Q..f. a,-;,-;eptiHg r eqti ire9 ~ u i tl:l. i A -t-RB- aggi;ime9 l oa9 i Hg 2eqtieA>Je iHtOP' ale , 6-A-d ffit.1-8-t- >J9AtiAtie -t-9 gperate tl-H-t-i-l- gff2ite pG-We-r-

~ ~ regtgre9 -t-9 -t-RB- ~ bi;ises ~ ,-;apabi l itieg .a-r reqi;iire9 -t-9 ~ m.t. .f..r.m .eo " ariety Q..f. iAitia l Q9A9iti9Ae ~

.a-g.+. JdG .H:+ ataA9by .w-i-t-l:+/- .t.J:+/-. @AgiAQ ~ 6-A-d JdG .H:+ ataH9by

.w-i-t4+ .t-l:J..@ @HgiHe a..t; eimbi@Ht Q9A9iti9Aa Additi9Aal JdG

,-;apabilitieg ffit.1-8-t- &!- dem9Aatrated -t-9 H\B-t- reqti i red

£tiP' eillaA>Jeg , e--.-g-.-, ,-;apability Q..f. -t-RB- JdG -t-9 re " ert -t-9 staAdby 2tati;ig ~ -e>H ECC£- 2igAal wh-i-1-e- gperatiAg .H:+ para l lel

.t-e-s-t. ~

Prgpgr geqneA>JiHg Q..f. l9a9a 1 iA>Jln9iAg trippiAg Q..f.

AQAOaaeHtieil lgagg , .i..e. .eo reqi;iire9 ftiA>Jti9A ~ JdG Qpgg llJH I. ITY I t is acceptab l e for divis i ons to be cross t i ed during shutdown conditions , permitting a s i ng l e offsite power circuit to supply all required AC e l ectrica l power distribution subsystems . No fast transfer capabi l ity is required for o ff site circuits to be considered OPERABLE for this LCO .

As described in Applicable Safety Analyses , in the event of an accident during shutdown , the TS are designed to maintain the p l ant in a condition s u ch that, e¥ef+ :w-i-t-A, ~ siAgle faili;ire , the p l ant will not be in immediate difficulty .

APPLICABILITY The AC sources required to be OPERABLE in MODES 4 and 5 and during movement of irradiated fuel assemblies i n the primary or secondary containment provide assurance that :

a. Systems that provide core cooling are ava i lable ;

b. Systems needed to mitigate a fuel handling accident are availab l e ;

(co n tinued )

CLI NTON B 3 . 8- 36 Rev i sion No . G-=6

AC Sources ~ Shutdown B 3.8.2 BASES ACTIONS C. 1 (continued )

additional required AC source is inoperable , and power is s t ill supplied to HPCS , 72 ho u rs is a l lowed to restore the additional required AC source to OPERABLE . This is reasonab l e cons i der i ng HPCS will st ill pe r fo r m i ts funct i on ,

absent an additional sing l e failure .

SURVEILLANCE SR 3.8.2.1 REQUIREMENTS SR 3 . 8 . 2 . 1 requires the SRs from LCO 3 . 8 . 1 that are necessary for ensuring the OPERABILITY of the AC sources in SR 3.8 .1.7, SR o t her tha ~MODES 1 , 2 , and 3 . SR 3 . 8.1 . 8 is not requ ired to 3.8.1.11, SR 3.8.1.12, be met sin e only one offsite circuit is required to be SR 3.8.1.13, SR OPERABLE . In MODES 4 and 5 ECCS injection/spray subsystems 3.8 .1.15, SR 3.8 .1.18, are manually controlled in accordance with LCO 3 . 5 . 2 ,

" Reactor Pressure Vesse l (RPV) Water I nventory Contro l." No and SR 3.8.1 .19 are ECCS initiation signals are credited for initiation of these not required to be met subsystems . Adequate time is availab l e to manually start because DG start and and load DGs from the Main Contro l Room in support of RPV load within a specified inventory contro l, if required . Therefore , SR 3 . 8 . 1 . 12 and SR 3 . 8 . 1 . 19 , which verify the DG ' s capability to start time and response on automatically on actual or simulated ECCS init i ation an offsite power or signa l s , are not required to be met i n MODES 4 and 5 .

ECCS initiation signal SR 3 . 8 . 1 . 17 is not required to be met because the required is not required. OPERABLE DG (s ) is not required to undergo periods of being synchronized to the offsite circuit . SR 3 . 8 . 1.20 is excepted because starting i ndependence is not required with the DG ( s ) that is not required to be OPERABLE . Refer to the corresponding Bases for LCO 3 . 8 . 1 for a discussion of each lwhich precludes <;: P' This SR is modified by a Note~~ ~ reasgn

.t.G preclYde requiring the OPERABLE DG (s ) from being

~ .t.fte. ~~

paral l eled with the offsite power network or otherwise rendered inoperable during the performance of SRs , and preclude de - energizing a required 4 .1 6 kV ESF bus or disconnecting a requ ired offsite circuit during performance of SRs . With l imited AC sources available , a single event could compromise both the required circuit and the DG . It is the intent that these SRs must sti l l be capable of being met , but actua l performance is not required for any DG or offsite circuit .

REFERENCES None .

CLINTON B 3 . 8 - 39 Rev i sion No . ~

RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements: Difference between revisions

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@@ Line 49: / Line 49: @@
 Exelon Generation Company, LLC (EGC), requests adoption of Technical Specifications Task Force Traveler 582 (TSTF-582), Revision 0, "Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements," 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, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station , Units 1 and 2, Technical Specifications (TS). The Technical Specifications (TS) related to RPV WIC are revised to incorporate operating experience and to correct errors and omissions in TSTF-542, Revision 2, "Reactor Pressure Vessel Water Inventory Control." The proposed changes also include the variation described in TSTF-583 and discussed in Reference 3.
-.0     ASSESSMENT 2.1     Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a letter dated August 13, 2020 (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station , Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.
+.0     ASSESSMENT 2.1     Applicability of Safety Evaluation EGC has reviewed the safety evaluation for TSTF-582 provided to the Technical Specifications Task Force in a {{letter dated|date=August 13, 2020|text=letter dated August 13, 2020}} (Reference 2). This review included a review of the NRC evaluation, as well as the information provided in TSTF-582 (Reference 1). As described below, EGC has concluded that the justifications presented in TSTF-582 and the safety evaluation prepared by the NRG are applicable to Clinton Power Station , Unit 1, Dresden Nuclear Power Station, Units 2 and 3, LaSalle County Station, Units 1 and 2, and Quad Cities Nuclear Power Station, Units 1 and 2, and justify this amendment for the incorporation of the changes to these plants TS.
 EGC verified that the required ECCS injection/spray subsystem can be aligned and the pump started using relatively simple evolutions involving the manipulation of a small number of components. These actions can be performed in a short time (less than the minimum Drain Time of 1 hour) from the control room following plant procedures.
 .2     Variations 2.2.1   Proposed TS Changes to Adopt TSTF-583-T, "TSTF-582 Diesel Generator Variation" TSTF-582, "RPV WIC Enhancements," states:

RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements: Difference between revisions

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3.0 REGULATORY ANALYSIS

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