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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20198L3331997-12-18018 December 1997 Safety Evaluation Supporting Approval of Proposed Merger of Atlantic Energy,Inc,& Delmarva Power & Light Co ML20212G8301997-10-24024 October 1997 Safety Evaluation Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively ML20198S2161997-10-24024 October 1997 Safety Evaluation Accepting Proposed Change to Provisions Identified in Rev 14 of PBAPS QAP Description Re Nuclear Review Board Meeting Frequency ML20217J5631997-10-0909 October 1997 Safety Evaluation Supporting Amend 225 to License DPR-56 ML20217J6161997-10-0707 October 1997 Safety Evaluation Re Alternative to Reactor Pressure Vessel Circumferential Weld Insps for Plant,Unit 3 ML20211L6241997-10-0303 October 1997 Safety Evaluation Authorizing Licensee Proposed Use of Code Case N-516-1 to Weld Modified Suction Strainer in Suppression Chamber at Plant ML20217D8161997-09-30030 September 1997 Safety Evaluation Supporting Amend 224 to License DPR-56 ML20211D6201997-09-17017 September 1997 SER Accepting VT-2 Examiner Qualification Request for PECO Energy Company,Peach Bottom Atomic Power Station,Units 2 & 3 ML20216G5601997-09-0404 September 1997 Safety Evaluation Supporting Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively ML20217M8001997-08-19019 August 1997 Safety Evaluation Supporting Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively ML20149L2841997-07-23023 July 1997 Safety Evaluation Accepting Licensee Relief Request RR-22 for Plant,Units 2 & 3 ISI Program ML20140B0371997-05-30030 May 1997 Safety Evaluation Accepting QAP Description Change ML20135B4111997-02-19019 February 1997 Safety Evaluation Supporting Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively ML20149L8681996-11-15015 November 1996 SER Accepting Core Spray Piping Insp & Flaw Evaluation for Plant,Unit 2 ML20149L2441996-01-29029 January 1996 Safety Evaluation Accepting Insp & Evaluation Methodology for Operation of Unit 3 Core Shroud for Duration of Current Operating Cycle,Performed in Response to GL 94-03 ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20057B6441993-09-16016 September 1993 SER Concluding That Safe Shutdown Capability at Plant, Satisfies Requirements of Section Iii.G & Iii.L of App R to 10CFR50 ML20126H9031992-12-23023 December 1992 Safety Evaluation Granting Relief from Inservice Insp Requirements for Facilities ML20127N4941992-11-17017 November 1992 Safety Evaluation Accepting Util 120-day Response to Suppl 1 to GL 87-02 ML20062C7501990-10-26026 October 1990 Safety Evaluation Re Evaluation of Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20246E0331989-08-21021 August 1989 SER Supporting Util Response to Generic Ltr 83-28,Item 2,1 (Parts 1 & 2).Programs Exist for Identifying safety-related Components Required for Reactor Trip Function & Vendor Interface W/Nmss Vendor for Required Components ML20205A8801988-10-31031 October 1988 Safety Evaluation of Util Plan for Restart of Peach Bottom Atomic Power Station ML20148P3351988-04-0101 April 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Program for All safety-related Components ML20148E6301988-01-15015 January 1988 SER Accepting Util 840116,0927 & 850805 Responses to Generic Ltr 82-33,Item 6 Re Compliance w/post-accident Monitoring Instrumentation Guidelines of Reg Guide 1.97 Concerning Emergency Response Facilities ML20236D0541987-10-22022 October 1987 Safety Evaluation Supporting Util Repts on Computer Program Analyses Methods Intended for Use in Part of Plant Core Reload Analyses ML20235D2431987-09-22022 September 1987 Safety Evaluation Re Proposed Onsite Storage of Liquid Oxygen & Hydrogen for Implementation of Hydrogen Water Chemistry.Permanent Hydrogen Water Installation Acceptable ML20209H0201987-04-24024 April 1987 Safety Evaluation Supporting Util Re Torus Attached Piping Mods - Mark I Program ML20204C1001986-07-24024 July 1986 Safety Evaluation Supporting Listed Util Responses & Actions Reviewed During Insp on 840913-19 Re Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20141F6071986-04-0808 April 1986 Safety Evaluation Granting Util Requests for Relief from Inservice Insp Requirements of ASME Code,Section XI ML20209C3141986-03-20020 March 1986 Safety Evaluation Supporting Shroud Head Connection Replacement at Facility,Per Util 860107 Submittal 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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p 1 UNITED STATES 2
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20086 4001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 224 AND 228TO FACILITY OPERATING
- LICENSE NOS. DPR-44 and DPR-56 PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION. UNIT NOS. 2 AND 3 '
DOCKET NOS. 50 277 AND 50-278
1.0 INTRODUCTION
By letter dated May 1,1998, as supplemented by letter dated September 11,1998, PECO Energy Company, the licensee for Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3, proposed a change to modify the safety relief valves (SRVs) Technical Specification (TS)
Surveillance Requirements (SRs) to perform manual actuations once every 24 months as part of each unit's startup testing activities. The specific TS change evaluated herein is for TS SRs 3.4.3.2 and 3.5.1.12. The current SR 3.4.3.2 requires verifying the opening of the SRVs when manually actuated, and SR 3.5.1.12 requires verifying the opening of the Automatic Depressurization System (ADS) SRVs when manually actuated. These SRs also contain associated notes which state that these tests are not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the tests. The licensee proposes to revise these SRs to require verification that the SRV actuators stroke when manually actuated in the depressurization mode. The licensee also proposes to delete the note associated with these SRs.
Each plant SRV is a Target Rock 3-Stage pilot-operated valve with an attached pneumatic actuator. There are a total of 11 SRVs installed on each of the Peach Bottom 2 and 3 main steam systems, all of which operate in the safety mode or the depressurization mode. In the safety mode, each SRV opens when system pressure exceeds the self-actuating setpoint pressure, which is controlled by the setpoint spring acting on the pilot disk. When the pilot disk opens, the resulting differential pressure across the second stage piston opens the second stage disk which then results in a differential pressure across the main piston which opens the main 1~
disk to relieve system overpressure. The depressurization mode functions are accomplished by applying electric power to solenoids which provide instrument gas to the pneumatic diaphragm assembly that forces the second stage disk to open. Once the second stage is open, steam pressure provides the necessary force to open the main SRV disk. All 11 SP.Vs are capable of being manually opened in the depressurization mode. Five of the SRVs also perform the ADS
- function which automatically opens the SRVs in the depressurization mode to reduce system i pressure following a small break LOCA.
i 9810150198 981005 "
PDR ADOCK 05000277 P PDR t
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2-Currently, the Peach Bottom 2 and 3'TS SRs 3.4.3.2 and 3.5.1.12 require that, at least once every 24 months, the SRVs be opened during reactor startup following an outage. The licensee states that there has been one occurrence of leakage in an SRV second stage disk caused by steam cutting of the seat and disk area that required a plant shutdown. The licensee states that the leak is suspected to have resulted from functional testing of the SRV during startup. The
- licensee also states that second stage leakage, if allowed to continually increase, will eventually result in opening of the main disk and system depressurization.
2.0 EVALUATION The licensee proposes to revise TS SRs 3.4.3.2 and 3.5.1.12 to require verification that only the SRV actuators stroke every 24 months. This would eliminate the requirement to open the SRVs during reactor startup following an outage. The notes associated with these SRs would also be eliminated since reactor steam pressure would no longer be required to meet the SRs. The i
licensee states that with the proposed changes, the solenoid valves would be energized, the actuators would stroke, and the movement of the second stage disks would be verified by the measurement of the travel of the actuator roG. However, because there would be no steam pressure, the main disks would not be lifted in situ. The licensee states that since the safety mode tests of approximately 50% of the SRVs are performed at a 24-month frequency to meet the requirements of the American Society of Mechanical Engineers (ASME) OM (Operations and i
Maintenance) Code - 1990 Edition, the only change in the frequency of testing of the SRV components is that the main disks of the SRVs would be tested every two cycles (approximately i 4 years) as compared to the current requirement of every one cycle (approximately 2 years). In addition to the safety mode tests, TS SRs 3.3.5.1.5 and 3.5.1.11 require tests of the ADS logic
- system and simulated automatic actuation tests of the ADS every 24 months. The licensee states that the combination of these tests, the safety mode testing, and that performed for SRs 3.4.3.2 and 3.5.1.12, completely demonstrates the operability of the SRVs.
The staff has reviewed the licensee's proposed TS changes and finds that the current TS requirement to perform the in situ stroke testing of the SRVs may contribute to undesirable SRV leakage and could result in spurious actuation of the valves during power operation. By removing the TS requirement to perform in situ functional testing during startup, the probability of inadvertent opening of an SRV may be reduced through the elimination of a potentialinitiator of SRV second stage disk leakage and subsequent erosion. The testing proposed by the licensee provides periodic verification of all of the individual SRV components which are currently being tested e.xcept that the main disks are to be stroke tested less frequently. The staff finds that the proposed TS surveillance and safety mode testing of the SRV components are acceptable because they provide assurance of adequate valve operation.
The licensee has proposed testing with less frequent stroking of the SRV main stages. Instead of stroke testing the SRV main stages after each refueling outage, only half would be stroke i
tested during safety mode testing each refueling outage, which would result in an approximate four year frequency. However, because the main stage disks of the Peach Bottom 2 and 3 valves and similar valves at other BWRs have a history of reliable performance, the staff finds that the proposed stroking of half of the main stage disks each refueling is adequate.
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. 3-Another difference between the current TS-requ!:wd stroking and the licensee's proposal is that, when performing the testing in situ as required by the current TS, the testing verifies that the SRV discharge line is not blocked. However, the licensee stated that foreign material exclusion controls in place at the plant, together with the horizontal orientation of the discharge line mating connections, provide reasonable assurance that no obstruction exists in the lines. The staff finds that the likelihood of blockage of an SRV discharge line is remote as demonstrated by l operational history and that the licensee has acceptably addressed this concem.
3.0 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.
4.0 ENVIRONMENTAL CONSIDERATION
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The amendments change a requirement with respect to installation or use of a facility component l located within the restricted area as defined in 10 CFR Part 20 and change the surveillance j requirements. 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, ed 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 ;
l comment on such finding (63 FR 40559). 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.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is l 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 Commission's 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: G. Hammer Date: October 5,1998 l
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