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| | PIIIIADELPIIIA ELECTRIC COMPANY Peach Bottm Atmic Power Station Unit No. 1 1985 Annual Dt h_ssion Report Docket No. 50-171 The following sununrizes the status.of the Peach Bottm Unit No.1 Decamission Facility for the year 1985, based on the scmi-annual inspections required by Technical Specification 8.2.4(a) . |
| | : 1. There is no significant danuge or structural deterioration observed in the security fence surrouncling the exclusion area. |
| | : 2. There is rr significant damge or structural deterioration observed in the containment vessel, scent fuel building enclosure, or radwaste rocm within the exclusion area. |
| | : 3. There is no significant damage or structural deterioration observed in the designated barricades within the exclusion area. |
| | : 4. There is no mndition observed indicating a degradation in security controls or procedures. |
| | : 5. There is no evidence of ground water nuvcment between the exclusion area and outside the exclusion area. (See the attached insoection sunmary.) |
| | : 6. There is no significant change in the radiation or con-tantination levels in the facility. |
| | : 7. There are no ranovable contamination levels above 100 drn. |
| | : 8. The radiation levels in all areas are less than 0.1 mR/hr. |
| | : 9. Maximum airborne activity was 1.2 X 10 -9 tCi/cc. Isotopic analysis identified the source to be a naturally occurring isotope. |
| | : 10. The absolute filter samplc on the containment equalization line indicated: |
| | Radiation Level - less than 0.1 mR/hr. |
| | Contanination Level - less thm 100 dpm. |
| | : 11. There were no reportable occurrences reported during the year to the NRC as required by Technical Specification 8.2.4(b) . |
| | 'I /Yf #f Sb Station Superintdndent 8604240231 851231 PDR ADOCK 05000171 R PDR |
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| | PEACH BOTTOM UNIT 1 CONTAINMENT AND EXCLUSION AREA INSPECTIONS 1985 INSPECTION |
| | |
| | ==SUMMARY== |
| | |
| | ST 12.21, the semi-annual Unit 1 Exclusion Area Inspection, was performed in January and August 1985. Neither of these inspections revealed any unacceptable physical or radiological conditions. In addition, periodic inspections were performed to monitor water conditions inside the exclusion area. As noted in the 1984 Unit 1 Annual Decommission Report, inspectio:ts of the exclusion area had revealed accumulations of water in the liquid radwaste room and in the containment lower basement. |
| | The water in the containment consista of a moisture spot in the lower base ment. While the size of the moisture spot varies slightly with time, there has not been any trend in either direction over the past two years. Currently, the spot is less than 10 square feet. |
| | Inspection of accessible containment penetrations revealed no pathway for rain water flow into the containment. An inspection of normally inaccessible areas inside the containment building was conducted. No additional areas with accumulating water were discovered. |
| | The source of water accumulating in the liquid radwaste room has been determined to be rain water leaking through an overhead access hatch. |
| | Accumulation has been correlated with rainfall. At present, no accumulation of water exists in the liquid radwastee room. Cox_ective action required to eliminate this source of water in leakage is currently being evaluated. |
| | Water samples obtained for radiological analysis and radiological surveys performed during all inspections have revealed no significant activity or radiation levels. There is no evidence of ground water movement between the containment and the outside. |
| | |
| | .I PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (215)841 4000 April 17, 1986 Docket No. 50-171 Mr. Robert M. Ber nero, Director Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 |
| | |
| | ==SUBJECT:== |
| | Peach Bottom Atomic Power Station Unit No. 1 1985 Annual Decommission Report |
| | |
| | ==Dear Mr. Muller:== |
| | |
| | Attached is the 1985 Peach Bottom Atomic Power Station Unit No. 1 Decommission Report. The report is submitted pursuant to reporting requirement 8.2.4(a) in Appendix A to License No. |
| | DPR-12. |
| | Very truly yours, |
| | ~ |
| | /){ |
| | W. M. Alden Engineer-In-Charge Licensing Section Nuclear Services LLM:vdw Attachment cc: Dr. T. E. Mt:rley, Administrator, Region I, USNRC Mr. T. P. J7hnson, Resident Site Inspector Distribution Schedule 0Y t i |
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Category:ANNUAL OPERATING REPORT
MONTHYEARML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20236T4521997-12-31031 December 1997 PBAPS Units 2 & 3 Annual 10CFR50.59 & Commitment Rev Rept for Period of 970101-1231 ML20198E8711996-12-31031 December 1996 PBAPS Units 2 & 3 Annual 10CFR50.59 Rept,Jan-Dec 1996 ML20113A6771995-12-31031 December 1995 PBAPS Unit 2 & 3 Annual 10CFR50.59 Rept,Jan-Dec 1995 ML20087H8251994-12-31031 December 1994 Annual 10CFR50.59 Rept,Jan-Dec 1994 ML20063J9211993-12-31031 December 1993 Pbaps,Units 1 & 2 Annual 10CFR50.59 Rept for Jan-Dec 1993 ML20046A2411992-12-31031 December 1992 1992 Pbaps,Units 1 & 2 Annual 10CFR50.59 Rept ML20044B8181992-12-31031 December 1992 Annual Decommission Rept 20 ML20128D3691991-12-31031 December 1991 Annual 10CFR50.59 Rept ML20086L4101990-12-31031 December 1990 1990 Annual 10CFR50.59 Rept.Rept Received W/O Page 63 ML20006E5711990-02-0707 February 1990 Rev to 1989 Annual Rept on Safety Relief Challenges at Plants ML20006B7141990-01-16016 January 1990 1989 Annual Rept on Safety Relief Challenges at Peach Bottom Atomic Station, Per TMI Action Plan Item II.K.3 ML20058J9581989-12-31031 December 1989 1989 Annual 10CFR50.59 Rept ML20245A2741989-04-13013 April 1989 1988 Annual Rept on Safety Relief Challenges at Peach Bottom Atomic Power Station (Rept 9) ML20247D3461988-12-31031 December 1988 1988 Annual 10CFR50.59 Rept ML20154A7381987-12-31031 December 1987 Decommissioning Rept 15,1987 ML20210A5541986-12-31031 December 1986 1986 Annual Decommissioning Rept 14 ML20211P1501985-12-31031 December 1985 1985 Annual Plant Mod Rept ML20203E4661985-12-31031 December 1985 1985 Annual Decommission Rept ML20203P5211984-12-31031 December 1984 Annual Plant Mod Rept,1984 ML20087P7521984-04-0202 April 1984 1983 Annual Rept on Safety-Relief Valve Challenges ML20091R2951983-12-31031 December 1983 Annual Plant Mod Rept,1983, ML20076E5231983-06-0909 June 1983 Annual Plant Mod Rept,1982 ML20058C3181982-07-19019 July 1982 Annual Plant Mod Rept,1981 ML20069C9141982-07-19019 July 1982 Annual Plant Mod Rept,1981 ML20010F7311981-08-25025 August 1981 Annual Plant Mod Rept,Jan-Dec 1980 ML19351A1571981-06-30030 June 1981 Semiannual Decommission Annual Operating Rept for 1981 ML20010E6471980-12-31031 December 1980 Annual Plant Mod Rept Jan-Dec 1980 ML19323G4131980-05-23023 May 1980 Decommissioned Annual Rept,1979 ML19225C1881979-07-19019 July 1979 Decommmission Annual Rept 1978 ML20067B5921977-12-31031 December 1977 Annual Operating Rept 2 for Jan-Dec 1977 ML20067B5291976-12-31031 December 1976 Annual Operating Rept 1 for 760101-1231. W/Undated Ltr 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000278/LER-1999-005-03, :on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With1999-10-20020 October 1999
- on 990920,uplanned Esfas During Planned Mod Activitives in Main CR Were Noted.Caused by Inattention to Detail by Individuals Performing Work.All CR Mods Were Ceased to Allow Review of Mod Work Packages.With
ML20217K9931999-10-14014 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 05000278/LER-1999-004-03, :on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held1999-10-0101 October 1999
- on 990901,3A RPS Bus Was Inadvertently Deenergized,During Planned Mod Activities on Main CR Panel. Caused by Electrician Failing to Self Check Work.All CR Work Was Ceased Immediately & Shutdown Meeting Held
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 ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 05000278/LER-1999-003-03, :on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With1999-09-13013 September 1999
- on 990814,HPCIS Was Declared Inoperable Due to Erratic Behavior Resulting in Loss of Single High Train Safety Sys.Caused by Weakness in Procedural Guidance. Readjusted Hydraulic Governor Needle Valve.With
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 05000277/LER-1999-005-01, :on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.With1999-07-16016 July 1999
- on 990616,failure to Maintain Provisions of FP Program Occurred.Caused by Less than Adequate Engineering Rigor in Both Development & Review Analysis.Fire Watch Immediately Established.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 05000278/LER-1999-002-02, :on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.With1999-05-0606 May 1999
- on 990406,safeguard Sys to Unrelated Door Was Inadvertently Disabled by Security Alarm Station Operator. Caused by Noncompliance with Procedures & Less than Adequate Shift Turnover.Briefed Personnel on Event.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 05000278/LER-1999-001-03, :on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments1999-04-0808 April 1999
- on 990312,ESF Actuation of Rcics Occurred Due to High Steam Flow Signal During Sys Restoration.Temporary Change to Restoration Procedure Was Initiated to Open RCIC Outboard Steam Isolation Valve in Smaller Increments
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 05000278/LER-1998-009-01, :on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with1999-01-20020 January 1999
- on 981227,unplanned Esfa Were Noted.Caused by Transformer Insulator Failure.Replaced Failed Insulator. with
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 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection 05000277/LER-1998-008-01, :on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With1998-12-30030 December 1998
- on 981130,circuit Breaker SU-25 Tripped.Caused by Less than Adequate Procedural Guidance.Operators Verified Sys Integrity & Successfully Returned Sys to Svc.With
05000277/LER-1998-007-02, :on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With1998-12-0404 December 1998
- on 981107,failure to Meet TS & Associated LCO Requirments of Absolute Difference in APRM & Calculated Power of Less than 2% Was Noted.Caused by Substitute Valves Being Used.Removed Substitute Valves.With
ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 05000278/LER-1998-005-03, :on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.With1998-11-20020 November 1998
- on 981025,inadvertent Unit 3 Electrical Bus E33 Trip (Esfa) During Performance of Unit 2 Electrical Bus E32 Surveillance Test Was Noted.Caused by Personnel Error. Sp S12M-54-E32-XXF4 Was Completed.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 05000277/LER-1998-006-02, :on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With1998-10-0909 October 1998
- on 980915,automatic RWCU Isolation Occurred While Placing RWCU Sys in Svc.Caused by Unexpected Surge of Water.Procedure Change Was Initiated to Open MO-2-12-74 & RWCU Sys Was Successfully Returned to Svc.With
ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 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 ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with 05000278/LER-1998-004-03, :on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc1998-09-18018 September 1998
- on 980820,automatic RWCU Isolation Occurred While Placing B RWCU Sys Demineralizer in Svc.Caused by less-than-adequate Control of Equipment.Isolated B Demineralizer & Returned RWCU Sys to Svc
05000277/LER-1998-005-02, :on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made1998-09-18018 September 1998
- on 980824,noted Failure to Meet TS Actions for Suppression chamber-to-drywell Vacuum Breaker Not Being Fully Seated.Caused by Personnel Failing to Take All TS Required Actions.Temporary Procedure Changes Were Made
ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 1999-09-30
[Table view] |
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PIIIIADELPIIIA ELECTRIC COMPANY Peach Bottm Atmic Power Station Unit No. 1 1985 Annual Dt h_ssion Report Docket No. 50-171 The following sununrizes the status.of the Peach Bottm Unit No.1 Decamission Facility for the year 1985, based on the scmi-annual inspections required by Technical Specification 8.2.4(a) .
- 1. There is no significant danuge or structural deterioration observed in the security fence surrouncling the exclusion area.
- 2. There is rr significant damge or structural deterioration observed in the containment vessel, scent fuel building enclosure, or radwaste rocm within the exclusion area.
- 3. There is no significant damage or structural deterioration observed in the designated barricades within the exclusion area.
- 4. There is no mndition observed indicating a degradation in security controls or procedures.
- 5. There is no evidence of ground water nuvcment between the exclusion area and outside the exclusion area. (See the attached insoection sunmary.)
- 6. There is no significant change in the radiation or con-tantination levels in the facility.
- 7. There are no ranovable contamination levels above 100 drn.
- 8. The radiation levels in all areas are less than 0.1 mR/hr.
- 9. Maximum airborne activity was 1.2 X 10 -9 tCi/cc. Isotopic analysis identified the source to be a naturally occurring isotope.
- 10. The absolute filter samplc on the containment equalization line indicated:
Radiation Level - less than 0.1 mR/hr.
Contanination Level - less thm 100 dpm.
- 11. There were no reportable occurrences reported during the year to the NRC as required by Technical Specification 8.2.4(b) .
'I /Yf #f Sb Station Superintdndent 8604240231 851231 PDR ADOCK 05000171 R PDR
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PEACH BOTTOM UNIT 1 CONTAINMENT AND EXCLUSION AREA INSPECTIONS 1985 INSPECTION
SUMMARY
ST 12.21, the semi-annual Unit 1 Exclusion Area Inspection, was performed in January and August 1985. Neither of these inspections revealed any unacceptable physical or radiological conditions. In addition, periodic inspections were performed to monitor water conditions inside the exclusion area. As noted in the 1984 Unit 1 Annual Decommission Report, inspectio:ts of the exclusion area had revealed accumulations of water in the liquid radwaste room and in the containment lower basement.
The water in the containment consista of a moisture spot in the lower base ment. While the size of the moisture spot varies slightly with time, there has not been any trend in either direction over the past two years. Currently, the spot is less than 10 square feet.
Inspection of accessible containment penetrations revealed no pathway for rain water flow into the containment. An inspection of normally inaccessible areas inside the containment building was conducted. No additional areas with accumulating water were discovered.
The source of water accumulating in the liquid radwaste room has been determined to be rain water leaking through an overhead access hatch.
Accumulation has been correlated with rainfall. At present, no accumulation of water exists in the liquid radwastee room. Cox_ective action required to eliminate this source of water in leakage is currently being evaluated.
Water samples obtained for radiological analysis and radiological surveys performed during all inspections have revealed no significant activity or radiation levels. There is no evidence of ground water movement between the containment and the outside.
.I PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 (215)841 4000 April 17, 1986 Docket No. 50-171 Mr. Robert M. Ber nero, Director Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
Peach Bottom Atomic Power Station Unit No. 1 1985 Annual Decommission Report
Dear Mr. Muller:
Attached is the 1985 Peach Bottom Atomic Power Station Unit No. 1 Decommission Report. The report is submitted pursuant to reporting requirement 8.2.4(a) in Appendix A to License No.
DPR-12.
Very truly yours,
~
/){
W. M. Alden Engineer-In-Charge Licensing Section Nuclear Services LLM:vdw Attachment cc: Dr. T. E. Mt:rley, Administrator, Region I, USNRC Mr. T. P. J7hnson, Resident Site Inspector Distribution Schedule 0Y t i
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