ML20154G655
| ML20154G655 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/01/1998 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154G653 | List: |
| References | |
| NUDOCS 9810130268 | |
| Download: ML20154G655 (15) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066H001 PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 l PEACH BOTTOM ATOMIC POWER STATION. UNIT NO,2 l AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 223 License No. DPR-44
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by PECO Energy Company, et al. (the licensee) dated l May 23,1997, as supplemented by letter dated September 11,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), ;
and the Commission's rules and regulations set forth in 10 CFR Chapter 1. !
B. The facility will operate in canformity with the application, the provisions of the Act, and the rules and 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 Commission's regulations; 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 Commission's 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 Facility Operating License No. DPR-44 is hereby amended to read as follows:
9810130268 981001 i PDR ADOCK 05000277 l P PDR
2 (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.223 , are hereby incorporated in the license. PECO Energy Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance, and is to be implemented within 30 days from its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1 +LJ o_. Q Robert A. Capra, Director Project Directorate 1-2 '
Division of Reactor Projects .1/11 Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 1, 1998
\
i ATTACHMENT TO LICENSE AMENDMENT NO.223 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 Replace the following pages of the Appendix A Technical Spec'd; .ations with the ericiosed pages.
The revised areas are indicated by marginal lines.
Effiove jngg.r1 5.0-17 5.0-17 5.0-18 5.0-18 8 3.6-4 B 3.6-4 8 3.6-5 B 3.6 5 8 3.6-29 8 3.6-29 i
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c _ _ __ _ . - . . _ _ . _ _ . _ _ _ _ . _ . _ - . _ _ _ -. _ _ _. _ _ _
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Proaram (SFDP) (continued) ;
- 1. A' required system redundant to system (s) supported by the inoperable support system is also inoperable; or
- 2. A required system redundant to system (s) in turn supported by the inoperable supported system is also inoperable; or
- 3. A required system redundant to support system (s) for .
the supported systems (b.1) and (b.2) above is also I inoperable.
]
- c. The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this l program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are '
required to be entered. I 5.5.12 Primary Containment Leakaae Rate Testina Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
l This pra ram shall be in accordance with the guidelines contained in Regulatory Cuide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. O, " Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Section 10.2:
- a. MSIV leakage is excluded from the combined total of 0.6 L.
for the Type B and C tests. l The peak calculated containment internal pressure for the design ;
basis loss of coolant accident, P., is 49.1 psig. '
The maximum allowable primary containment leakage rate, L., at P.,
shall t,e 0.5% of primary containment air weight per day.
Leakage Rate acceptance criteria are:
- a. Primary Containment leakage rate accepance criterion is s 1 .0 L.. During the first unit startup following testing in ,
o a:cordance with this program, the leakage rate acceptance l criteria are s 0.60 L for the Type B and Typ. C tests and s i 0.75 L. for Type A tests; '
icontinued) ;
4 210, 2!4 PBAPS UNIT 2 5.0-17 Amendment No. 223 9
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Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Prima v Centainment Leakaae Rate Testina Proaram (continued) l
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is s S000 sec/ min when tested at a P.,
l c. MSIV leakage acceptance criteria are as specified in SR i 3.6.1.3.14. ,
1 The provisions of SR 3.0.2 do not apply to the test frequencies i specified in the Primary Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
210, 2!#
PBAPS UNIT I 5.0-18 Amendment No. 223
l Primary Containment B 3.6.1.1 BASES l
SURVEILLANCE S R' 3.6.1.1.1 (continued)
REQUIREMENTS valve leakage (SR 3.6.1.3.14), does not necessarily result in a failure of this SR. The impact of the failure to meet these SRs must be evaluated against the Type A, B, and C '
acceptance criteria of the Primary Containment Leakage Rate !
l Testing Program. At s 1.0 L. the offsite dose consequences l are bounded by the assumptions of the safety analysis. The i Frequency is required by the Primary Containment Leakage i Rate Testing Program.
SR 3.6.1.1.2 Maintaining the pressure suppression function of primary l containment requires limiting the leakage from the drywell to the suppression chamber. Thus, if an event were to occur l that pressurized the drywell, the steam would be directed I through the downcomers into the suppression pool. This SR is a leak test that confirms that the bypass area between the drywell and the suppression chamber is less than or equivalent to a one-inch diameter hole (Ref. 4). This ensures that the leakage paths that would bypass the suppression pool are within allowable limits. !
The leakage test is performed every 24 months. The 24 month l Frequency was developed considering that component failures that might have affected this test are identified by other primary containment SRs. Two consecutive test failures, however, would indicate unexpected primary containment degradation; in this event, as the Note indicates, a test shall be performed at a Frequency of once every 12 months until two consecutive tests pass, at which time the 24 month test Frequency may be resumed.
(continued)
PBAPS UNIT 2 8 3.6-4 Revision No.
Amendment No. 223
l Primary Containment B 3.6.1.1 1
BASES (continued) i REFERENCES 1.' UFSAR, Section 14.9.
l
- 2. Letter G94-PEPR-183, Peach Bottom Improved Technical ;
Specification Project Increased Drywell and l Suppression Chamber Pressure Analytical Limits, from l G.V. Kumar (GE) to A.A. Winter (PECO), August 23, 1994.
- 3. 10 CFR 50, Appendix J, Option B. l
- 4. Safety Evaluation by the Office of Nuclear Reactor Regulation Supporting Amendment Nos. 127 and 130 to Facility Operating License Nos. DPR-44 and DPR-56, dated February 18, 1988.
- 5. NEI 94-01, Revision 0, " Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J."
- 6. ANSI /ANS-56.8-1994, " Containment System Leakage Testing Requirements."
- 7. Peach Bottom Atomic Power Station Evaluation for Extended Final Feedwater Reduction, NEDC-32707P, Supplement 1, Revision 0, May, 1998.
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l PBAPS UNIT 2 B 3.6-5 Revision No.
Amendment No. 223
PCIVs B 3.6.1.3 j BASES SURVEILLANCE SR' 3.6.1.3.13 REQUIREMENTS (continued) This SR ensures that in case the non-safety grade instrument air system i:; unavailable, the SGIG System will perform its i design function to supply nitrogen gas at the required pressure for valve operators and valve seals supported by the SGIG System. The 24 month Frequency was developed ;
considering it is prudent that this Surveillance be performed only during a plant outage. Operating experience has shown.that these components will usually pass this Surveillance when performed at the 24 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.6.1.3.14 Leakage through each MSIV must be s 11.5 scfh when tested at
. a P. (25 psig). The analyses in Reference 1 are based on treatment cf MSIV leakage as a secondary containment bypass leakage, independent of a primary to secondary containment leakage analyzed at 1.27 L.. In the Reference I analysis all i
4 steam lines are assumed to leak at the TS Limit. This ensures that MSIV leakage is properly accounted for in determining the overall impacts of primary containment leakage. The Frequency is required by the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.15 Verifying the opening of each 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve is restricted by a blocking device to less than er equal to the required maximum opening angle specified in the UFSAR (Ref. 4) is required to ensure that the valves can close under DBA conditions within the times in the analysis of Reference 1. If a LOCA occurs, the purge and exhaust valves must close to maintain primary containment leakage within the values assumed in the accident analysis. At other times pressurization concerns are not present, thus the purge and exhaust valves can be fully open. The 24 month Frequency is appropriate because the blocking devices may be removed during a refueling outage.
(continued)
PBAPS UNIT 2 B 3.6-29 Revision No.
Amendment No. 223
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[ps k UNITED STATES g j e
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 o
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PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE l Amendment No227 License No. DPR-56
- 1. The Nuclear Regulatory Commission (the Commission) has founo that:
A. The application for amendment by PECO Energy Company, et al. (the licensee) dated May 23,1997, as supplemented letter dated September 11,1998, complies with the ,
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), l and the Commission's rules ant; regulations set forth in 10 CFR Chapter I. I B. The facility will operate in conformity with the application, the provisions of the Act, an j the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can bo conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 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 Commission's regulations and all app!! cable requirements have been satisfied.
- 2. A;cordingly, 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 Facility Operating License No. DPR-56 is hereby amended to read as follows:
l 2
l (2) I_ochnical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 227, are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifmations.
l 3. This license amendment is effective as of its date of issuance, and is to be implemented within 30 days from the date of its issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION T N CL (ps Robert A. Capra, Director Project Directorate 1-2 Division of Reactor Projects .1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 1
Date of issuance: October 1, 1998 l
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.. . . - . . . . - - . . . - . - . . . - . . . ...~-- . . - - - - . .
ATTACHMENT TO LICENSE AMENDMENT NO. 227 FAClLITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
Remove g 5.0-17 5.017 5.0 18 5.018 8 3.6-4 8 3.6-4 B 3.6-5 B 3.6 5 B 3.6-29 B 3.6-29 t
i e
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Safety Function Determination Proaram (SFDP) (continued)
- 1. A required system redundant to system (s) supported by the inoperable support system is also inoperable; or
- 2. A required system redundant to system (s) in turn supported by S.: inoperable supported system is also inoperable; or
~
- 3. A required system redundant to support system (s) for the supported systems (b.1) and (b.2) above is also inoperable.
- c. The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
5.5.12 Primary Containment Leakaae Rate Testina Proaram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. O, " Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J," Section 10.2:
- a. MSIV leakage is excluded from the combined total of 0.6 L.
for the Type B and C tests.
The peak calculated containment internal pressure for the design basis loss of coolant cccident, P., is 49.1 psig.
The maximum allowable primary containment leakage rate, L., at P.,
shall be 0.5% of primary containment air weight per day.
Leakage Rate acceptance criteria are:
- a. Primary Containment leakage rate acceptance criterion is s 1.0 L.. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are s 0.60 L. for the Type B and Type C teste and s 0.75 L. for Type A tests; icontinued)
PBAPS UNIT 3 5.0-17 Amendment No. BA4, Zyg, 227
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment leakaae Rate Testina Proaram (continued)
- b. Air lock testing accentance criteria are:
- 1) Overall air lock leakage rate is s 9000 sec/ min when tested at a P..
- c. MSIV leakage acceptance criteria are as specified in SR 3.6.1.3.14..
The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
J PBAPS UNIT 3 5.0-18 Amendment No. 214,279 227
4 _._ , ._ . . _ . . _ _ . _ . _ . . _ . _ _ _ _ . _ . _ _ _ . . _ . _ _ . _ _ . . _ . . _ . _ . _ _ . _
. B 3.6.1.1 BASES SURVEILLANCE SR '3.6.1.1.1 (continued)
REQUIREMENTS valve leakage (SR 3.6.1.3.14), does not necessarily result in a failure of this SR. The impact of the failure to meet these SRs must be evaluated against the Type A, B, and C acceptance criteria of the Primary Containment Leakage Rate l Testing Program. At s 1.0 L. the offsite dose consequences are bounded by the assumptions of the safety analysis. The Frequency is required by the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.1.2 Maintaining the pressure suppression function of primary containment requires limiting tne leakage from the drywell to the suppression chamber. Thus, if an event were to occur i that pressurized the drywell, the steam would be directed l -through the downcomers into the suppression pool. This SR is a leak test that confirms that the bypass area between the drywell and the suppression chamber-is less than or equivalent to a one-inch diameter hole (Ref. 4). 'This l
ensures that the leakage paths that would bypass the suppression pool are within allowable limits.
l The leakage test is performed every 24 months. The 24 month Frequency was developed considering that component failures that might have affected this test are identified by other primary containment SRs. Two consecutive test failures, however, would indicate unexpected primary containment degradation; in this event, as the Note indicates, a test shall be performed at a Frequency of once every 12 months until two consecutive tests pass, at which time the 24 month test Frequency may be resumed.
(continued) i i-
- PBAPS UNIT 3 B 3.6-4 Revision No.
Amendment No. 227 1
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Primary Containment l B 3.6.1.1 l l
BASES (continued) l REFERENCES 1.' UFSAR, Section 14.9.
- 2. Letter G94-PEPR-183, Peach Bottom Improved Technical Specification Project Increased Drywell and I Suppression Chamber Pressure Analytical Limits, from 4
G.V. Kumar (GE) to A.A. Winter (PECO), August 23, 1994.
3.
I 10 CFR 50, Appendix J, Option B.
A
- 4. Safety Evaluation by the Office of a : lear Reactor 3
Regulation Supporting Amendment Nos. 127 and 130 to Facility Operating License Nos. DPR-44 and DPR-56, dated February 18, 1988.
- 5. NEI 94-01, Revision 0, " Industry Guideline for Implementing Performance-Based Option of 10 CFR Part l 50, Appendix J."
- 6. ANSI /ANS-56.8-1994, " Containment System Leakage Testing Requirements."
- 7. Peach Bottom Atomic Power Station Eval;ation for Extended Final Feedwater Reduction, NEDC-32707P, Supplement 1, Revision 0, May, 1998.
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t i
k PBAPS UNIT 3 9 3.6-5 Revision No.
Amendner.t :L. 227
PCIVs B 3.6.1.3 BASES SURVEILLANCE SR' 3.6.1.3.13 REQUIREMENTS (continued) This SR ensures that in case the non-safety grade instrument
, air system is unavailable, the SGIG System will perform its i
design function to supply nitrogen gas at the required pressure for valve operators and valve seals supported by the SGIG System. The 24 month Frequency was developed considering it is prudent that this Surveillance be performed only during a plant outage. Operating experience has shown that these components will usually pass this Surveillance when performed at the 24 month Frequency.
Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.
SR 3.6.1.3.14 Leakage through each MSIV must be s 11.5 scfh when tested at a P. (25 psig). The analyses in Reference 1 are based on treatment of MSIV leakage as a secondary containment bypass leakage, independent of a primary to secondary containment leakage analyzed at 1.27 L.. In the P.eference 1 analysis all 4 steam lines are assumed to leak at the TS Limit. This ensures that MSIV leakage is properly accounted for in determining the overall impacts of primary containment leakage. The Frequency is required by the Primary Containment Leakage Rate Testing Program.
SR 3.6.1.3.15 Verifying the opening of each 6 inch and 18 inch primary containment purge valve and each 18 inch primary containment exhaust valve is restricted by a blocking device to less than or equal to the required maximum opening angle specified in the UFSAR (Ref. 4) is required to ensure that the valves can close under DBA conditions within the times in the analysis of Reference 1. If a LOCA occurs, the purge and exhaust valves must close to maintain primary containment leakage within the values assumed in the accident analysis. At other times pressurization concerns c'. not present, thus the purge and exhaust valves can be fully open. The 24 month Frequency is appropriate be:ause j the blocking devices may be removed during a refueling i outage.
(continued)
PBAPS UNIT 3 B 3.6-29 Revision No.
Amendment No. 227
- ny, , , - - . , ,,-