ML073531054
| ML073531054 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/10/2007 |
| From: | Braun R Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LCR S07-02, LR-NO7-0296, TSTF-448, Rev 3 | |
| Download: ML073531054 (5) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC DEC 10 2007 10CFR50.90 LR-N07-0296 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 SALEM GENERATING STATION - UNIT 1 AND UNIT 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 NRC DOCKET NOS. 50-272 AND 50-311
Subject:
SUPPLEMENT TO APPLICATION TO REVISE TECHNICAL SPECIFICATIONS (LCR S07-02) REGARDING CONTROL ROOM ENVELOPE HABITABILITY IN ACCORDANCE WITH TSTF-448, REVISION 3, USING THE CONSOLIDATED LINE ITEM IMPROVEMENT PROCESS
Reference:
(1). LR-N07-0058, "Application to Revise Technical Specifications (LCR S07-02) Regarding Control Room Envelope Habitability In Accordance With TSTF-448, Revision 3, Using The Consolidated Line Item Improvement Process," dated April 15, 2007.
(2). E-mail, Richard B. Ennis to Jeffrie J. Keenan, "Supplement needed for LCR S07 TSTF-448 (TAC Nos. MD5367 and MD5368)", Dated November 8, 2007.
By letter dated April 15, 2007 (Reference 1), PSEG Nuclear LLC (PSEG) submitted a proposed Technical Specifications (TS) amendment for the Salem Generating Station Unit 1 and Unit 2. The proposed amendment includes a change to Section 6.0, Administrative Controls, for both Units 1 and 2 Technical Specifications inserting a new specification 6.18 (Unit 1) and 6.17 (Unit 2) describing the Control Room Envelope Habitability Program. The Reference 2 email pointed out that Attachment 2 of the Reference 1 submittal included identical extraneous statements (one for each of the Unit 1 and 2 marked-up pages 6-31) referring to exceptions to Sections C.1 and C.2 of Regulatory Guide 1.197 that do not exist. This same statement appears in the Revised Technical Specification Pages. to this letter provides the corrected marked-up and revised pages 6-31 provided in Reference 1 above. The extraneous statement has been removed as requested by the Reference 2 e-mail.
95-2168 REV. 7/99
I DEC 10 2007 Document Control Desk Page 2 LR-N07-0296 PSEG has determined that the information contained in this letter and attachment does not alter the conclusions reached in the 10CFR50.92 no significant hazards analysis previously submitted.
If you should have any questions regarding this submittal, please contact Mr. Jeffrie Keenan at (856) 339-5429.
I declare under penalty of perjury that the foregoing is true and correct.
Executedon _"_/,_° __
(Date)
Sincerely, Robert Braun Site Vice President Salem Generating Station
Attachment:
(1)
C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Salem Unit 1 and Unit 2 and Hope Creek Mail Stop 08C2 Washington, DC 20555-0001 USNRC Senior Resident Inspector - Salem Generating Station Mr. P. Mulligan, Acting Manager Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625
ATTACHMENT 1 License Amendment Request Salem Generating Station Units 1 & 2 NRC Docket Nos. 50-272 and 50-311 Supplement to TSTF-448 Control Room Envelope Habitability Proposed Technical Specification Changes (Marked-up) Pages Revised Technical Specification Pages
The following replaces the proposed Technical Specification change (Marked-up) pages 6-31 for Salem Units 1 & 2 submitted by PSEG Nuclear LLC letter LR-N07-0058, dated April 15, 2007 in Attachment 2:
MARKED UP TECHNICAL SPECIFICATION PAGES Salem Generatinq Station Unit 1 Technical Specification Page 6-31 Salem Generating Station Unit 2 Technical Specification Page 6-31
ADMINISTRATIVE CONTROLS
- c. Proposed changes to the Bases that require either condition of Specification 6.17.b above shall be reviewed and approved by the NRC prior to Implementation.
- d. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).
- e. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
/
/ 6*18 CONTROL.ROOM ENVELOPE HBBITA33ILITY PRO A Control Room Envelope (CRE) Habitability Program shall be established and implemented 'to ensure that C3.E habitability is maintained such that, with an CFEEiFiBLE Control Room Emergency Air Conditioning System (CREACS), CRE occupants can control the rekctor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, ora{
smoke challenge. The program shall ensure that adequate radiation protection IS provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
I The program shall include the following elements:
\ a.
b.
The definition of the CRE and the CRE boundary.
Requirements for maintaining the CRE boundary in its design condition II including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CAE boundary during the pressurization mode of operation by one train of the CREACS, operating at the flow rate required by the Surveillance Reqilirements, at a frequency of 36 months on a STAGGE3ED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e. The quantitative limits on ~nfilteredair inleakage into the CXE. These limits shall be stated in a manner to allow direct cox~parisonto the unfiltered air inleakage measured by the teseinq described in paragraph
- c. The upfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure chat exposure of CRE occupants to these hazards wiil be withic the assumptions in the licensing basis.
The provisions of Surveillance Requirements 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered ioleakage, and'measuring CRE pressure and assessing the CRZ boundary as required by paragraphs c and d, respectively.
SALEM - UNIT 1 6-31 Amendment No. xxx
I ADMINISTRATIVE CONTROLS 6.17 CONTROL ROOM ENVELOPE HABITABILITY PROGRAM A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Air Conditioning System (CREACS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provsded to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
The program shall include the following elements:
I I
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas.adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREACS, operating at the flow rate
. required by the Surveillance Requirements, at a frequency of 36 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph
- c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of Surveillance Requirement 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
I SALEM - UNIT 2
\
The following replaces the revised Technical Specification pages submitted by PSEG Nuclear LLC letter LR-N07-0058, dated April 15, 2007 in Attachment 4:
REVISED TECHNICAL SPECIFICATION/BASES PAGES Salem Generating Station Unit 1 Technical Specification Page 6-31 Salem Generating Station Unit 2 Technical Specification Page 6-31
ADMINISTRATIVE CONTROLS
\ c. Proposed changes to the Bases that require either condition of Specification 6.17.b above shall be reviewed and approved by the NRC prior to Implementation.
- d. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71 (e).
- e. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
6.18 CONTROL ROOM ENVELOPE ITABILITY PROG A Control goom Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Air Conditioning System (CREACS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CXE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
The program shall include the following elements:
- b. Requirements for maintaining the CRE boundary in its design condition
-including configuration control and preventive maintenance.
- I 1' L.
n Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREACS, operating at the flow rate required by the Surveillance Requirements, at a frequency of 36 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CAE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph
- c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the asslnptions in the licensing basis.
- f. -ihe provisions of Surveillance Requirements 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
\J
)
SALEM - UNIT 1 6-31 Amendment No. xxx
ADMINISTRATIVE CONTROLS A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Air Conditioning System (CREACS), CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
The program shall include the following elements:
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.l and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the CREACS, operating at the flow rate required by the Surveillance Requirements, at a frequency of 36 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph
- c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.
- f. The provisions of Surveillance Requirement 4.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
SALEM - UNIT 2 Amendment No. xxx