ML021400462
| ML021400462 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/17/2002 |
| From: | Colburn T NRC/NRR/DLPM/LPD1 |
| To: | Byram R Susquehanna |
| Colburn T, NRR/DLPM, 415-1402 | |
| References | |
| TAC MB3640, TAC MB3641 | |
| Download: ML021400462 (14) | |
Text
May 17, 2002 Mr. Robert G. Byram Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 2 North Ninth Street Allentown, PA 18101
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: ADOPTION OF NRC-APPROVED GENERIC CHANGES TO IMPROVED TECHNICAL SPECIFICATIONS (TAC NOS. MB3640 AND MB3641)
Dear Mr. Byram:
The Commission has issued the enclosed Amendment No. 203 to Facility Operating License No. NPF-14 and Amendment No. 177 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2. These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 10, 2001.
These amendments revise TS 3.7.3, Control Room Emergency Outside Air Supply (CREOAS)
System, to establish a new condition and required action to address degradation of the control room habitability envelope pressure boundary. Specifically, the changes allow the control room habitability envelope boundary to be opened intermittently under administrative control. A new condition is also added that allows 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the control room habitability envelope to operable status before entry into shutdown Limiting Condition for Operation 3.0.3 is required.
These changes are based on Technical Specifications Task Force-287, Revision 5, to the Standard Technical Specifications.
R. Byram A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
Timothy G. Colburn, Sr. 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. 203 to License No. NPF-14
- 2. Amendment No. 177 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: See next page
R. Byram Susquehanna Steam Electric Station, Units 1 &2 Bryan A. Snapp, Esq Assoc. General Counsel PPL Services Corporation 2 North Ninth Street GENTW3 Allentown, PA 18101-1179 Rocco R. Sgarro Supervisor-Nuclear Licensing PPL Susquehanna, LLC 2 North Ninth Street GENA61 Allentown, PA 18101-1179 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469 PPL Susquehanna, LLC Nuclear Records Attn: G. DallaPalu 2 North Ninth Street GENA62 Allentown, PA 18101-1179 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Bryce L. Shriver Vice President-Nuclear Site Operations Susquehanna Steam Electric Station PPL Susquehanna, LLC Box 467, NUCSA4 Berwick, PA 18603-0035 Herbert D. Woodeshick Special Office of the President PPL Susquehanna, LLC Rural Route 1, Box 1797 Berwick, PA 18603-0035 George T. Jones Vice President-Nuclear Engineering & Support PPL Susquehanna, LLC 2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 203 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 December 10, 2001, 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. 203 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: May 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 203 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 3.7-6 3.7-6 3.7-7 3.7-7 3.7-8 3.7-8
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 177 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 December 10, 2001, 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. 177 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: May 17, 2002
ATTACHMENT TO LICENSE AMENDMENT NO. 177 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 3.7-6 3.7-6 3.7-7 3.7-7 3.7-8 3.7-8
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 203 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 177 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 letter dated December 10, 2001, PPL Susquehanna, LLC (PPL, the licensee), submitted a request for changes to the Susquehanna Steam Electric Station, Units 1 and 2 (SSES-1 and 2),
Technical Specifications (TSs). The requested changes revise TS 3.7.3, Control Room Emergency Outside Air Supply (CREOAS) System, to establish a new limiting condition for operation and required actions to address degradation of the control room habitability envelope pressure boundary. Specifically, the changes allow the pressure boundaries of the CREOAS System to be opened intermittently under administrative control. The changes also allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to restore the capability to maintain proper pressure in the control room habitability envelope before entry into shutdown Limiting Condition for Operation (LCO) 3.0.3 is required.
These changes are based on Technical Specifications Task Force (TSTF)-287, Revision 5, to NUREG-1433, Standard Technical Specifications for General Electric Plants (BWR/4),
Revision 1.
2.0 REGULATORY EVALUATION
Surveillance Requirement (SR) 3.7.3.4 tests the integrity of the control room habitability envelope boundary and requires a positive pressure limit to be satisfied with one CREOAS subsystem operating. While other SRs in TS 3.7.3 of the SSES-1 and 2 TSs test the operability of the subsystems (i.e., heaters, filters, and actuation signals), SR 3.7.3.4 ensures that control room habitability envelope pressure boundary leak tightness is adequate to meet design-basis assumptions. However, there are no corresponding Conditions, Required Actions, and Completion Times associated with this boundary surveillance.
Currently, if the control room habitability envelope pressure boundary is breached, neither CREOAS subsystem will be able to maintain the positive pressure required by SR 3.7.3.4.
Such a condition renders both subsystems inoperable, and requires entry into LCO 3.0.3 (during operation in MODES 1, 2, or 3).
Section 6.5.1 of the Standard Review Plan (SRP) requires control room habitability systems to meet the standards of Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A, General Design Criteria (GDC) 4, 5, and 19. For this situation, only GDC 19 is applicable. GDC 19 requires the control room to provide operators with adequate protection from the effects of radiation during a design basis accident. This requirement forms the regulatory acceptance criteria for the licensees request.
The proposed changes to the TSs incorporate TSTF-287, Revision 5, to allow 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (during operation in MODES 1, 2, or 3) to restore the capability to maintain proper pressure before requiring the units to perform an orderly shutdown. The changes also allow intermittent opening of the control room habitability envelope under administrative control.
On August 11, 2000, NRC staff approved a similar amendment incorporating TSTF-287 criteria into the TSs at Duane Arnold Energy Center.
3.0 TECHNICAL EVALUATION
The proposed changes to LCO 3.7.3 are as follows:
- a.
A new Condition B is added to LCO 3.7.3 to specify that 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are allowed to restore an inoperable control room habitability envelope to operable status. All other Conditions have been administratively re-labeled to support this change.
b.
Condition E of LCO 3.7.3 for two CREOAS subsystems inoperable in MODES 1, 2, or 3 is modified to exclude entry into LCO 3.0.3 when the subsystems are inoperable due to an inoperable control room habitability envelope.
c.
A note is added which allows the control room habitability envelope boundary to be opened intermittently under administrative controls.
The staff reviewed the requirements of TSTF-287, Revision 5 for applicability to the licensees request, and the SRP requirements for the control room habitability envelope.
The proposed changes would adopt TSTF-287, Revision 5, without changes except for use of nomenclature that is consistent with SSES-1 and 2 system and equipment designations.
Upon implementation of the proposed changes, if the control room habitability envelope pressure boundary is inoperable in MODES 1, 2, or 3 such that the CREOAS subsystems cannot establish or maintain the required pressure, the boundary must be restored within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In TSTF-287, the staff concluded that requiring the plant to immediately enter LOC 3.0.3 when the control room habitability envelope is not intact is excessive, and that allowing the 24-hour Completion Time gives the licensee ample time to effect repairs on the system. The staff also considered the 24-hour Completion Time to be reasonable based on the low probability of a design-basis accident (DBA) occurring during this time period and compensatory measures available to the operator to minimize the consequences of potential hazards.
To maintain consistency in LCO 3.7.3 pursuant to the addition of new Condition B, existing Condition D (re-labeled as Condition E) must also be modified to allow continued operations in MODES 1, 2, or 3 if the CREOAS subsystems are inoperable due to an inoperable control room habitability envelope.
LCO 3.7.3 is modified by a note allowing the control room habitability envelope boundary to be opened intermittently under administrative controls. For entry and exit through doors, the administrative control of the opening is performed by the person(s) entering or exiting the area.
For other openings, a dedicated individual, who is in continuous communication with the control room, is stationed at the opening. In its letter dated December 10, 2001, the licensee states that this individual will have a method to rapidly close the opening when a need for control room habitability envelope isolation is indicated.
In its letter dated December 10, 2001, the licensee states that during the period that the control room habitability envelope pressure boundary is inoperable, it shall take appropriate compensatory measures consistent with the intent of GDC 19 to protect control room personnel from potential hazards such as radiation, radioactive contamination, toxic chemicals, smoke, temperature and relative humidity, and to ensure physical security. The compensatory measures will be available to address these concerns for intentional and unintentional entry into the proposed new Condition B.
Based on the low probability of a DBA occurring during the 24-hour Completion Time associated with Condition B, the availability of compensatory measures consistent with GDC 19 to minimize the consequences during an event, and the implementation of the administrative controls mentioned in the above evaluation, the NRC staff concludes that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions 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 10014). Accordingly, the amendments meet 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.
5.0 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 amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: E. Thomas Date: May 17, 2002
R. Byram A copy of our safety evaluation is also enclosed. Notice of Issuance will be included in the Commissions Biweekly Federal Register Notice.
Sincerely,
/RA/
Timothy G. Colburn, Sr. 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. 203 to License No. NPF-14
- 2. Amendment No. 177 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC PDI-1 Reading SRichards RLaufer TColburn MOBrien OGC WBecker ACRS BPlatchek, RGN-I GHill(4)
Tech Branch EThomas RDennig ACCESSION NO.: ML021400462 OFFICE PDI-1/PM PDI-1/PM PDI-2/LA RORP OGC PDI-1/SC NAME TColburn EThomas MOBrien RDennig JHeck RLaufer DATE 4/29/02 4/29/02 4/29/02 5/2/02 5/9/02 5/14/02 OFFICIAL RECORD COPY