ML031560495

Issuance of Amendments Intermittent Opening of Isolated Flow Paths and Tip Isolation

ML031560495
Person / Time
Site:	Susquehanna
Issue date:	06/05/2003
From:	Richard Guzman NRC/NRR/DLPM/LPD1
To:	Shriver B Susquehanna
Guzman R, NRR/DLPM 415-1030
References
TAC MB6665, TAC MB6666, TS 3.3.6.1, TS.5.5.10
Download: ML031560495 (16)

Text

June 5, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: INTERMITTENT OPENING OF ISOLATED FLOW PATHS AND TIP ISOLATION (TAC NOS. MB6665 AND MB6666)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 213 to Facility Operating License No. NPF-14 and Amendment No. 188 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 31, 2002.

These amendments revise Technical Specifications (TSs) Section 3.3.6.1, Primary Containment Isolation Instrumentation, to add an ACTIONS Note allowing intermittent opening, under administrative control, of penetration flow paths that are isolated. Additionally, these amendments revise TSs to breakout the traversing incore probe system isolation as a separate isolation Function with an associated Required Action to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than immediately initiating a unit shutdown. As stated in your application, changes to the Bases for TS 3.3.6.1 will be addressed in accordance with TS 5.5.10, TS Bases Control Program.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely,

/RA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 213 to License No. NPF-14

2. Amendment No. 188 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page

June 5, 2003 Mr. Bryce L. Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: INTERMITTENT OPENING OF ISOLATED FLOW PATHS AND TIP ISOLATION (TAC NOS. MB6665 AND MB6666)

Dear Mr. Shriver:

The Commission has issued the enclosed Amendment No. 213 to Facility Operating License No. NPF-14 and Amendment No. 188 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station (SSES), Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 31, 2002.

These amendments revise Technical Specifications (TSs) Section 3.3.6.1, Primary Containment Isolation Instrumentation, to add an ACTIONS Note allowing intermittent opening, under administrative control, of penetration flow paths that are isolated. Additionally, these amendments revise TSs to breakout the traversing incore probe system isolation as a separate isolation Function with an associated Required Action to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than immediately initiating a unit shutdown. As stated in your application, changes to the Bases for TS 3.3.6.1 will be addressed in accordance with TS 5.5.10, TS Bases Control Program.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.

Sincerely,

/RA/

Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 213 to License No. NPF-14

2. Amendment No. 188 to License No. NPF-22

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC PDI-1 RF RLaufer RGiardina ACRS RGuzman MOBrien RDennig GHill (4) OGC BPlatchek, RGN-1 ACCESSION NO.: ML031560495 *SE dtd, no changes made OFFICE PDI-1/PM PDI-2/LA RORP OGC PDI-1/SC NAME RGuzman MO'Brien RDennig* RHoefling RLaufer DATE 5/23/03 5/27/03 02/21/03 6/3/03 6/4/03 OFFICIAL RECORD COPY

Susquehanna Steam Electric Station, Units 1 & 2 cc:

Bryce L. Shriver Michael H. Crowthers Senior Vice President and Chief Nuclear Supervising Engineer Officer Nuclear Regulatory Affairs PPL Susquehanna, LLC PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENA61 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Richard L. Anderson Dale F. Roth Vice President - Nuclear Operations Manager - Quality Assurance PPL Susquehanna, LLC PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Berwick, PA 18603-0467 Aloysius J. Wrape, III Herbert D. Woodeshick General Manager - Nuclear Assurance Special Office of the President PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENA92 634 Salem Blvd., SSO Allentown, PA 18101-1179 Berwick, PA 18603-0467 Terry L. Harpster Bryan A. Snapp, Esq General Manager - Plant Support Assoc. General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSA4 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Robert A. Saccone Supervisor - Document Control Services General Manager - Nuclear Engineering PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENTW3 769 Salem Blvd., NUCSB3 Allentown, PA 18101-1179 Berwick, PA 18603-0467 Richard W. Osborne Rocco R. Sgarro Allegheny Electric Cooperative, Inc.

Manager - Nuclear Regulatory Affairs 212 Locust Street PPL Susquehanna, LLC P.O. Box 1266 Two North Ninth Street, GENA61 Harrisburg, PA 17108-1266 Allentown, PA 18101-1179 Director - Bureau of Radiation Protection Curtis D. Markley Pennsylvania Department of Supervisor - Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC P.O. Box 8469 769 Salem Blvd., NUCSA4 Harrisburg, PA 17105-8469 Berwick, PA 18603-0467 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035

Susquehanna Steam Electric Station, Units 1 & 2 cc:

Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803

PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 213 License No. NPF-14

1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A. The application for the amendment filed by PPL Susquehanna, LLC, dated October 31, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 213 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 5, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 213 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.3-52 3.3-52 3.3-62 3.3-62

PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 188 License No. NPF-22

1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that:

A. The application for the amendment filed by the PPL Susquehanna, LLC, dated October 31, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 188 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance and shall be implemented within 60 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 5, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 188 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.3-52 3.3-52 3.3-62 3.3-62

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 213 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 188 TO FACILITY OPERATING LICENSE NO. NPF-22 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 388

1.0 INTRODUCTION

By application dated October 31, 2002, PPL Susquehanna, LLC (PPL, the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).

The proposed amendments would revise TSs Section 3.3.6.1, Primary Containment Isolation Instrumentation, to add an ACTIONS note allowing intermittent opening, under administrative control, of penetration flow paths that are isolated, and to breakout the traversing incore probe (TIP) system isolation as a separate isolation Function with an associated Required Action to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than immediately initiating a unit shutdown.

2.0 REGULATORY EVALUATION

The U.S. Nuclear Regulatory Commission (NRC) staff finds that PPL in its October 31, 2002, submittal identified the applicable regulatory requirements. The regulatory requirements and guidance which the NRC staff considered in its review of the application are as follows:

1. The criteria for inclusion of limiting conditions for operation (LCOs) in the TSs are given in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36(c)(2)(ii).

2. Precedent as contained in generic change, TSTF-306, Revision 2, to NUREG-1433, Revision 1, Standard Technical Specifications [STS] for General Electric Plants (BWR/4), dated April 1995.

The primary containment isolation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). 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). Primary containment isolation within the time limits specified for those isolation valves designed to close automatically ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analysis for a DBA.

The TIP System isolation ball valves, which are only open when the TIP system is in use, receive isolation signals from the Primary Containment Isolation Function, as specified in Table 3.3.6.1-1, Function 2.a (Reactor Vessel Water Level - Low Level 3) and 2.d (Drywell Pressure -

High). As such, an inoperability of the Primary Containment Isolation Function affecting only the TIP instrumentation would require a unit shutdown. Isolation of the TIP System penetration flow paths in a design-basis event is assumed to be accomplished by manually actuating the shear (squib) valves. It should be noted, however, that the Unit 1 TIP System is powered from an auxiliary instrument bus which has an uninterruptible power supply and hence, the TIP drive mechanisms and ball valve controls for Unit 1 will still function in the event of a loss of offsite power.

3.0 TECHNICAL EVALUATION

3.1 Proposed TS Changes PPL proposes the following changes to SSES 1 and 2 TS 3.3.6.1:

1. Adds a Note 1 to the Action Notes that states Penetration flow paths may be unisolated intermittently under administrative controls. The existing note on separate condition entry now becomes Note 2.

2. Revises the Completion Time of Condition A from 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 2.a, 2.d, and 6.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.d, and 6.b to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 2.a, 2.d, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.d, 6.b, 7.a and 7.b.

3. Adds Function 7, Traversing Incore Probe Isolation along with its appropriate Applicable MODES, Required Channels, Conditions, SRs, and Allowable Values to Table 3.3.6.1-1, Primary Containment Isolation Instrumentation.

4. Revises the Bases for TS 3.3.6.1 to address the above changes.

3.2 Evaluation of Change TS 3.3.6.1 currently requires a unit shutdown in the event of an inoperability of the TIP instrumentation. PPL is proposing to allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to isolate the affected TIP penetration flow paths. In addition, the proposal would allow intermittent opening, under administrative control, of penetration flow paths that are isolated. The changes are consistent with TSTF-306. The proposed amendments would also modify the TS Bases to describe the proposed changes and provide supporting information. In its submittal, PPL indicated that adopting the provisions of TSTF-306 provides a significant benefit to the operation of SSES 1 and 2, in that it serves to provide consistency between the requirements for equipment and the instrumentation that supports the equipment, and additional flexibility in the performance of maintenance and repair activities.

Prior to the Approval of TSTF-306, STS 3.3.6.1 would not allow intermittent opening, under administrative controls, of penetration flow paths isolated due to inoperable primary containment isolation instrumentation and would require a shutdown in the event of an

inoperability of the TIP instrumentation. TSTF-306 revised STS 3.3.6.1 and its associated Bases to be consistent with requirements of STS 3.6.1.3, Primary Containment Isolation Valves, with respect to administratively opening isolated penetration flow paths and to be consistent with the Actions in STS 3.3.6.1 for inoperable manual isolation functions.

The Actions for the SSES 1 and 2 TS 3.3.6.1 would be modified by the addition of a Note allowing intermittent opening, under administrative control, of penetrations that are isolated to comply with Actions, surveillance requirements (SRs), or operating conditions. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. The primary containment isolation instrumentation serves as a support system for the primary containment isolation valves. Current SSES 1 and 2 TS 3.6.1.3, Primary Containment Isolation Valves, contains an Action Note which allows penetrations isolated due to Actions, SRs, and operating conditions to be intermittently opened under adminstrative control. The accident consequences are not affected by the allowance of isolated penetrations to be intermittently opened under administrative control due to an inoperable PCIV of its associated instrumentation. Since the Actions for inoperability of the instrumentation need not be more restrictive than the inoperability of the function it supports, the addition of Action Note 1 is acceptable.

The SSES 1 and 2 TS 3.3.6.1 would be further modified to breakout the TIP System isolation as a separate isolation instrumentation Function with an associated Required Action to isolate the penetration within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> rather than having to immediately initiate a unit shutdown. TIP System isolation in a design-basis event (with a loss of offsite power) would be accomplished by manual actuation of the shear valves. Additionally, the Actions for inoperable primary containment isolation instrumentation that requires a unit shutdown is overly restrictive in the event that the inoperability affects only the TIP isolation instrumentation. The proposed Action for the inoperability of this Function is the same as for inoperable manual isolation Functions (i.e., isolate the penetration in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />). This is because the TIP system penetration is a small bore (approximately 1/2 inch), and its isolation in a design-basis event is via the manually operated shear valves. The ability to manually isolate the TIP System by either the normal isolation valve or the shear valve isolation Functions provides an appropriate level of safety.

Therefore, the NRC staff finds the proposed changes acceptable and consistent with the STS and TSTF-306.

3.3 Summary The NRC staff has reviewed the request by PPL to revise the TSs for SSES 1 and 2. The proposed change is consistent with the STS and TSTF-306 and provides reasonable assurance of overall plant safety. Based on the review, the NRC staff concludes that the proposed changes are acceptable. Although the licensees application included wording for the revised Bases discussion for TS 3.3.6.1, the licensee will formally address the change to the Bases in accordance with the TS Bases Control Program described in TS 5.5.10.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Pennsylvania State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (67 FR 78523). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (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.

Principal Contributors: R. Giardina R. Guzman Date: June 5, 2003