Text

Units 1 and 2, License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates
	ML21340A255
Person / Time
Site:	Hatch
Issue date:	12/06/2021
From:	Gayheart C; Southern Nuclear Operating Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	NL-21-0722
	Download: ML21340A255 (45)
	v • d • e

Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316 cagayhea@southernco.com December 6, 2021 Docket Nos.: 50-321 NL-21-0722 50-366 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Southern Nuclear Operating Company Edwin I. Hatch Nuclear Plant - Units 1 and 2 License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates Ladies and Gentlemen:

Pursuant to the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), Southern Nuclear Operating Company (SNC) hereby requests a license amendment to Edwin I. Hatch Nuclear Plant (HNP) Unit 1 Renewed Facility Operating License DPR-57 and Unit 2 Renewed Facility Operating License NPF-5. The proposed amendment requests adoption of Technical Specifications Task Force (TSTF)-207-A, Revision 5, Completion Time for Restoration of Various Excessive Leakage Rates, specifically, the amendment proposes administrative changes and changes to Completion Times for restoring leakage rates of Primary Containment Isolation Valves (PCIVs). These changes are consistent with the Improved Technical Specifications (NUREG-1433).

The enclosure provides a description and assessment of the proposed changes. provides the existing Technical Specifications (TS) pages marked to show the proposed change. Attachment 2 provides revised (clean) TS pages. Attachment 3 provides the existing TS Bases pages marked to show revised text associated with the proposed TS changes and is provided for information only.

SNC requests approval of the proposed amendment by December 31, 2022. The proposed changes would be implemented within 90 days after issuance of the amendment.

There are no regulatory commitments made in this submittal.

In accordance with 10 CFR 50.91, a copy of this application, with attachments, is being provided to the designated Georgia Official.

If you should have any questions regarding this submittal, please contact Ryan Joyce at 205.992.6468.

U.S. Nuclear Regulatory Commission NL-21-0722 Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 6th day of December 2021.

Respectfully submitted, Cheryl A. Gayheart Regulatory Affairs Director Southern Nuclear Operating Company CAG/tle

Enclosure:

Description and Assessment Attachments: 1. Proposed Technical Specifications Changes (Mark-Up)

2. Revised Technical Specifications Pages

3. Proposed Technical Specifications Bases Changes (Mark-Up) -

For Information Only cc: NRC Regional Administrator, Region II NRC NRR Project Manager - Hatch NRC Senior Resident Inspector - Hatch Director, Environmental Protection Division - State of Georgia RType: CHA02.004

Southern Nuclear Operating Company Edwin I. Hatch Nuclear Plant - Units 1 and 2 License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates Enclosure Description and Assessment

Enclosure to NL-21-0722 Description and Assessment 1.0

SUMMARY

DESCRIPTION Southern Nuclear Operating Company (SNC) requests amendments to the Technical Specifications (TS) for the Edwin I. Hatch Nuclear Plant (HNP), Unit Nos. 1 and 2. The proposed change incorporates Technical Specifications Task Force (TSTF)-207-A, Completion Time for Restoration of Various Excessive Leakage Rates, Revision 5 (Reference 1). Portions of TSTF-207-A were incorporated into the Hatch TS as part of Amendments No. 195 (HNP Unit 1) and No. 135 (HNP Unit 2) (Reference 2). These Amendments were issued on March 3, 1995 and implemented the Boiling Water Reactor (BWR) Owners Group Standard Technical Specifications (STS), NUREG-1433, Standard Technical Specifications General Electric Plants, BWR/4. Implementation of STS at Hatch predated NRC approval of TSTF-207-A, Revision 5, which occurred on June 13, 2000. Therefore, the proposed changes to incorporate the remaining portions of TSTF-207-A, Revision 5, are requested.

TSTF-207-A, Revision 5, modifies NUREG-1433, TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs). TS 3.6.1.3, Conditions A and B are revised to include penetration flow paths that have more than 2 PCIVs in series. The words except due to leakage not within limit are replaced with for reasons other than Condition D for TS 3.6.1.3, Conditions A, B, and C, to be consistent with NUREG-1433 Revision 5. This change is considered administrative. TS 3.6.1.3, Condition D is also revised to call out individual types of penetration flow paths and provide separate Completion Times for each penetration flow path type.

Associated TS Bases are revised to reflect these TS changes.

2.0 DETAILED DESCRIPTION 2.1 Existing Technical Specifications TS 3.6.1.3, Conditions A and B both contain a Note stating that the Condition is only applicable to penetration flow paths with two PCIVs. TS 3.6.1.3, Condition A requires entry if one or more penetration flow paths have one PCIV inoperable except when that inoperability is due to leakage not within limit. TS 3.6.1.3, Condition B requires entry if one or more penetration flow paths have two PCIVs inoperable except when that inoperability is due to leakage not within limit.

TS 3.6.1.3, Condition C is applicable to penetration flow paths with only one PCIV and requires entry if one or more such penetration flow paths have one PCIV inoperable except when that inoperability is due to leakage not within limit.

TS 3.6.1.3, Condition D requires entry when one or more penetration flow paths have leakage not within the specified limit and has a Required Action to restore leakage to within limit. Condition D has a Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.2 Reason for Proposed Change The Note of TS 3.6.1.3, Conditions A and B, states that the Conditions are only applicable to penetration flow paths with two PCIVs. This license amendment request proposes revising the Note such that it applies to penetration flow paths with two or more PCIVs. Similarly, TS 3.6.1.3, Condition B is revised to require entry when one or more penetration flow paths with two or more PCIVs are inoperable. Some penetration flow paths may have more than two PCIVs in E-1

Enclosure to NL-21-0722 Description and Assessment series in the flow path (e.g., in some cases a third qualified isolation valve downstream of the outboard valve.) This change will clarify that TS 3.6.1.3 Conditions A and B entry is the appropriate action for inoperable PCIVs in penetration flow paths with more than two PCIVs.

Additionally, TS 3.6.1.3, Conditions A, B and C all contain an exception for situations where PCIV inoperability is due to leakage rates not within limits. TS 3.6.1.3, Conditions A, B, and C will be reworded such that the exception will be for PCIV inoperability for reasons other than Condition D. This change eliminates potential questions regarding what leakages are being referred to in TS 3.6.1.3, Conditions A, B, and C. Since TS 3.6.1.3, Condition D requires entry for leakage not within limits, this change is considered administrative. This change is proposed to make TS 3.6.1.3, Conditions A, B, and C consistent with phrasing of exceptions in NUREG-1433, Revision 5.

For a Main Steam Isolation Valve (MSIV) inoperability, for reasons other than not meeting the MSIV leakage rate limit, TS 3.6.1.3, Required Action A.1 currently allows 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to restore the inoperability or isolate the penetration. For an MSIV not meeting the MSIV leakage rate limit, TS 3.6.1.3, Condition D currently requires restoration to within limits with a Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . As a result, there appears to be a conflict between Required Action A.1 Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and Required Action D.1 Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , in the event of an MSIV inoperability. The proposed change clarifies when TS 3.6.1.3, Condition D should be entered by listing individual penetration flow path leakage types and providing Completion Times of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for secondary containment bypass leakage and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for MSIV leakage. This change makes the Completion Times of TS 3.6.1.3, Condition D consistent with those of TS 3.6.1.3, Condition A.

TSTF-207-A, Revision 5, also adds a separate TS 3.6.1.3, Condition D Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for Excess Flow Check Valves (EFCVs) with leakage not within limits. For an EFCV inoperability, for reasons other than not meeting the EFCV leakage rate limit, TS 3.6.1.3, Required Action C.1 currently allows 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the inoperability or isolate the penetration. For an EFCV not meeting the EFCV leakage rate limit, TS 3.6.1.3, Condition D currently requires restoration to within limits with a Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . As a result, there appears to be a conflict between Required Action C.1 Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and Required Action D.1 Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , in the event of an EFCV inoperability. The proposed change clarifies when TS 3.6.1.3, Condition D should be entered by listing individual penetration flow path leakage types and providing Completion Times of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV leakage. This change makes the Completion Times of TS 3.6.1.3, Condition D consistent with those of TS 3.6.1.3, Condition C.

2.3 Description of Proposed Change Southern Nuclear Operating Company (SNC) requests an amendment to the TS for the HNP, Unit Nos. 1 and 2. The proposed change incorporates TSTF-207-A as follows.

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Enclosure to NL-21-0722 Description and Assessment Current TS 3.6.1.3 CONDITION Proposed TS 3.6.1.3 CONDITION A. ----------------------NOTE------------------- A. ----------------------NOTE-------------------

Only applicable to penetration flow Only applicable to penetration flow paths with two PCIVs. paths with two or more PCIVs.

One or more penetration flow paths One or more penetration flow paths with one PCIV inoperable except due with one PCIV inoperable except due to to leakage not within limit. leakage not within limit for reasons other than Condition D.

B. ----------------------NOTE------------------- B. ----------------------NOTE-------------------

Only applicable to penetration flow Only applicable to penetration flow paths with two PCIVs. paths with two or more PCIVs.

One or more penetration flow paths One or more penetration flow paths with two PCIVs inoperable except due with two or more PCIVs inoperable to leakage not within limit. except due to leakage not within limit for reasons other than Condition D.

C. ----------------------NOTE------------------- C. ----------------------NOTE-------------------

Only applicable to penetration flow Only applicable to penetration flow paths with only one PCIV. paths with only one PCIV.

One or more penetration flow paths One or more penetration flow paths with one PCIV inoperable except due with one PCIV inoperable except due to to leakage not within limit. leakage not within limit for reasons other than Condition D.

TS 3.6.1.3 Condition D currently appears as follows:

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow D.1 Restore leakage 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months paths with leakage not within limit. to within limit.

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Enclosure to NL-21-0722 Description and Assessment TS 3.6.1.3 Condition D is revised as follows:

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow D.1 Restore leakage 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for secondary paths with leakage secondary to within limit. containment bypass containment bypass leakage leakage rate, MSIV leakage rate, or EFCV leakage rate not within limit. AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for MSIV leakage AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV leakage The associated TS 3.6.1.3 Bases will also be revised, in accordance with TSTF-207-A, Revision 5, to reflect these changes.

See the attached marked up pages for HNP Units 1 and 2, included in Attachment 1, for the details concerning the specific changes. Attachment 2 provides revised (clean) TS pages. provides the existing TS Bases pages marked to show revised text associated with the proposed TS changes and is provided for information only.

There are no deviations from the preapproved TSTF-207-A, Revision 5, in the proposed HNP TS changes.

3.0 TECHNICAL EVALUATION

The Nuclear Regulatory Commission (NRC) did not issue a letter approving TSTF-207-A, Revision 5; however, it was incorporated by the NRC into Revision 2 of the Improved Standard Technical Specifications NUREGs. The provisions of TSTF-207-A have been adopted by other plants as part of complete conversion to Improved Standard Technical Specifications.

The addition of or more to the Note of TS 3.6.1.3, Conditions A and B, ensures the Conditions are applicable to penetration flow paths with more than two PCIVs. Similarly, the addition of or more to TS 3.6.1.3, Condition B ensures entry when one or more penetration flow paths with two or more PCIVs are inoperable, except when that inoperability is due to leakage not within limit, is appropriate because some penetration flow paths may have more than two PCIVs in series in the flow path. This change will clarify that TS 3.6.1.3 entry is the appropriate action for inoperable PCIVs in penetration flow paths with more than two PCIVs.

The revision of except due to leakage not within limit in TS 3.6.1.3, Conditions A, B and C to for reasons other than Condition D does not change how TS 3.6.1.3 is implemented. Since TS 3.6.1.3, Condition D requires entry for leakage not within limits, this change does not alter when entry into TS 3.6.1.3, Conditions A, B, C, or D is required. Therefore, this change is considered administrative.

TS 3.6.1.3 Condition A currently allows an 8-hour Completion Time for MSIV inoperability due to reasons other than leakage not within MSIV limits. Currently, TS 3.6.1.3, Condition D E-4

Enclosure to NL-21-0722 Description and Assessment Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for MSIV inoperability due to leakage not within limits is inconsistent with that of TS 3.6.1.3, Condition A for MSIVs. The revision of TS 3.6.1.3, Required Action D.1 Completion Time for MSIVs leakage rate not within limit from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months makes the Completion Time of Condition D consistent with that of Condition A. As stated in the Bases for TS 3.6.1.3, the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for the MSIV allows a period of time to restore the MSIV to OPERABLE status given the fact that MSIV closure will result in isolation of the main steam line(s) and a potential for plant shutdown. The extension to the time period to restore the MSIV leakage rate, when two MSIVs in one penetration are inoperable due to leakage, is considered to be acceptable since TS 3.6.1.3, Note 4 continues to provide assurance that MSIV leakage does not adversely impact Primary Containment OPERABILITY during the extended time period by requiring entry into TS 3.6.1.1, Primary Containment, Conditions.

TS 3.6.1.3 Condition C currently allows a 72-hour Completion Time for EFCV inoperability due to reasons other than leakage not within EFCV limits. The addition of a separate TS 3.6.1.3, Condition D Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV inoperability due to leakage not within limits makes the Completion Time of Condition D consistent with that of Condition C for EFCV inoperability for reasons other than leakage not within limits. As stated in the Bases for TS 3.6.1.3, the Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore EFCV operability is reasonable considering the EFCVs act as a penetration isolation boundary and the small pipe diameter of the affected penetrations. An EFCV inoperability due to leakage not within limits is a comparable level of degradation to an EFCV inoperability for reasons other than leakage not within limits, i.e., failure to close or failure to maintain pressure boundary. Therefore, it is not necessary for EFCV inoperability due to leakage not within limits to have a more restrictive Completion Time than the NRC approved Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV inoperability for reasons other than leakage not within limits.

4.0 REGULATORY ANALYSIS

4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.36, Technical specifications 10 CFR 50.36(c)(2)(ii) states: A technical specification limiting condition for operation of a nuclear reactor must be established for each item meeting one or more of the following criteria:

(C) Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs), satisfies Criterion 3 of 10 CFR 50.36(c)(2)(ii).

The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) to within limits. Primary containment isolation ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a DBA.

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Enclosure to NL-21-0722 Description and Assessment Appendix A to 10 CFR 50, General Design Criteria [GDC] for Nuclear Power Plants contains the following pertinent criteria:

Criterion 16 - Containment design. Reactor containment and associated systems shall be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.

Criterion 53 - Provisions for containment testing and inspection. The reactor containment shall be designed to permit (1) appropriate periodic inspection of all important areas, such as penetrations, (2) an appropriate surveillance program, and (3) periodic testing at containment design pressure of the leaktightness of penetrations which have resilient seals and expansion bellows.

Criteria 16 and 53 specify that the reactor containment is maintained, with periodic verification, an essentially leak-tight barrier. These criteria, however, do not contain actions required to be taken if leakage rates are exceeded.

It is noted HNP Unit 2 was licensed to the 10 CFR 50, Appendix A, GDC.

However, HNP Unit 1 was not licensed to the 10 CFR 50, Appendix A, GDC.

HNP Unit 1 was licensed to the applicable Atomic Energy Commission (AEC) preliminary general design criteria identified in Federal Register 32 FR 10213, published July 11, 1967 (ADAMS Accession No. ML043310029). The applicable AEC proposed criteria were compared to the 10 CFR 50, Appendix A, GDC, as documented in the Hatch Updated Final Safety Analysis Report (UFSAR),

Appendix F, "Conformance to the Atomic Energy Commission (AEC) Criteria."

Following implementation of the proposed change, HNP Unit 1 will remain in compliance with applicable AEC design criteria as described in the HNP Unit 1 UFSAR. Therefore, this difference does not alter the conclusion that the proposed changes are applicable to HNP Unit 1.

4.2 Precedent As previously discussed, TSTF-207-A, Revision 5, has been incorporated by the NRC into Revision 2 of the Improved Standard Technical Specifications NUREGs. The provisions of TSTF-207-A have been adopted by other plants as part of complete conversion to Improved Standard Technical Specifications. The Amendment issued to North Anna Power Station (Reference 3) is one example.

Additionally, the NRC issued Amendment 208 to Entergys Columbia Generating Station which incorporated several generic TS changes associated with containment isolation valves, including TSTF-207-A, Revision 5 changes (Reference 4).

4.3 No Significant Hazards Consideration Analysis In accordance with 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit, Southern Nuclear Operating Company (SNC), requests an amendment to the Technical Specifications (TS) for Edwin I.

Hatch Nuclear Plant (HNP), Units 1 and 2 to adopt Technical Specifications Task Force (TSTF)-207-A, Revision 5, Completion Time for Restoration of E-6

Enclosure to NL-21-0722 Description and Assessment Various Excessive Leakage Rates. The proposed change has been reviewed considering applicable requirements of 10 CFR 50.36; 10 CFR 50, Appendix A; and other applicable NRC documents. SNC has evaluated the proposed changes and determined that the change does not involve a Significant Hazards Consideration. SNC has evaluated if 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 amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No There are no changes to the plant configuration assumed for any accident.

The changes specified in TSTF-207-A, Revision 5, addressed individually below, cannot adversely affect the probability or consequences of accidents previously evaluated.

The addition of or more to the Note of TS 3.6.1.3, Conditions A and B, ensures the Conditions are applicable to penetration flow paths with more than two primary containment isolation valves (PCIVs). The addition of or more to Condition B to ensures entry when one or more penetration flow paths with two or more PCIVs are inoperable. This change is necessary because some penetration flow paths may have more than two PCIVs in series in the flow path. This change clarifies that TS 3.6.1.3 entry is the appropriate action for inoperable PCIVs in penetration flow paths with more than two PCIVs and has no impact on any accident initiator or accident mitigation.

The revision of except due to leakage not within limit in TS 3.6.1.3, Conditions A, B and C to for reasons other than Condition D does not change how TS 3.6.1.3 is implemented. This change does not alter when entry into TS 3.6.1.3, Conditions A, B, C, or D is required. Therefore, this change is considered administrative and has no impact on any accident initiator or accident mitigation.

The revision of TS 3.6.1.3, Required Action D.1 Completion Time for MSIV leakage rate not within limit from 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months makes the Completion Time of Condition D consistent with that of Condition A. The extension to the time period to restore the MSIV leakage rate, when two MSIVs in one penetration are inoperable due to leakage, is considered to be acceptable since Note 4 of TS 3.6.1.3 continues to provide assurance that MSIV leakage does not adversely impact Primary Containment OPERABILITY during the extended time period by requiring entry into TS 3.6.1.1, Primary Containment. The ability of the containment to meet its design function and mitigate the consequences of an accident are unchanged.

The addition of a separate TS 3.6.1.3, Condition D Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV inoperability due to leakage not within limits makes the Completion Time of TS 3.6.1.3, Condition D consistent with that of TS 3.6.1.3, E-7

Enclosure to NL-21-0722 Description and Assessment Condition C for EFCV inoperability for reasons other than leakage not within limits. EFCVs are installed on instrument line penetrations that provide acceptable barriers in the event that the single isolation valve fails.

The PCIVs are not an initiator of any accident previously evaluated. The consequences of a previously evaluated accident during the extended Completion Times are the same as the consequences during the existing Completion Times.

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

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

Response: No No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of the proposed changes. All systems, structures, and components previously required for the mitigation of a transient remain capable of fulfilling their intended design functions. The proposed changes have no adverse effects on any safety-related system or component and do not challenge the performance or integrity of any safety related system.

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

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

Response: No The changes made in accordance with TSTF-207-A, Revision 5, do not impact the leakage limits for primary containment isolation valves. There are no effects on the plant safety analyses.

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

Based on the above, SNC 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.

4.4 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions 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.

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Enclosure to NL-21-0722 Description and Assessment 5.0 ENVIRONMENTAL EVALUATION 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. 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.

6.0 REFERENCES

1. Technical Specification Task Force (TSTF)-207-A, Revision 5, Completion Time for Restoration of Various Excessive Leakage Rates, dated March 24, 2000

2. Letter from NRC to Georgia Power Company, Issuance of Amendments - Edwin I.

Hatch Nuclear Plant, Units 1 and 2, dated March 3, 1995 (ML013060412)

3. Letter from NRC to Virginia Electric and Power Company, North Anna Power Station, Units 1 and 2 - Issuance of Amendments Re: Conversion to Improved Technical Specifications, dated April 5, 2002 (ML021200265)

4. Letter from NRC to Energy Northwest, Columbia Generating Station - Issuance of Amendment Re: Adoption of Approved Generic Technical Specification Changes Associated with Containment Isolation Valves, dated September 15, 2008 (ML081900507)

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Southern Nuclear Operating Company Edwin I. Hatch Nuclear Plant - Units 1 and 2 License Amendment Request: Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates Attachment 1 Proposed Technical Specifications Changes (Mark-Up)

PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

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

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

1. Penetration flow paths except for 18 inch purge valve penetration flow paths may be unisolated intermittently under administrative controls.

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

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable 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 for Only applicable to penetration flow path by main steam line penetration flow paths with use of at least one two or more PCIVs. closed and de-activated AND

automatic valve, closed manual valve, blind 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main One or more penetration flange, or check valve steam line flow paths with one PCIV with flow through the inoperable except due to valve secured.

leakage not within limitfor reasons other than Condition D. AND (continued)

HATCH UNIT 1 3.6-7 Amendment No. 290

PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 ------------NOTES-----------

1. Isolation devices in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days for penetration flow path is isolation devices isolated. outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment B. -------------NOTE--------------- B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one two or more PCIVs. closed and de-activated

automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two or more PCIVs inoperable except due to leakage not within limitfor reasons other than Condition D.

(continued)

HATCH UNIT 1 3.6-8 Amendment No. 279

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. ---------------NOTE------------- C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by excess flow check penetration flow paths with use of at least one valve (EFCV) line and only one PCIV. closed and de-activated penetrations with a

automatic valve, closed closed system manual valve, or blind One or more penetration flange. AND flow paths with one PCIV inoperable except due to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for leakage not within limitsfor AND EFCV line and reasons other than penetrations with a Condition D. C.2 -----------NOTES---------- closed system

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Isolation devices that are locked, sealed, or otherwise secured may be verified by administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

D. One or more penetration D.1 Restore leakage to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for secondary flow paths with leakage within limit. containment bypass secondary containment leakage bypass leakage rate, MSIV leakage rate, or EFCV AND leakage rate not within limit. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for MSIV leakage AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCV leakage HATCH UNIT 1 3.6-9 Amendment No. 308

PCIVs 3.6.1.3 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 Completion Time of Condition A, B, C, AND or D not met.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months HATCH UNIT 1 3.6-9 Amendment No. 308