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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20195K3531999-06-15015 June 1999 Correction to Safety Evaluation Supporting Amend 129 to License NPF-30.Page 3 of SE Contained Editorial Error & Two Clarifications ML20195H1371999-05-28028 May 1999 Safety Evaluation Supporting Amend 133 to License NPF-30 ML20207B6181999-05-21021 May 1999 Safety Evaluation Supporting Amend 132 to License NPF-30 ML20205S1161999-04-20020 April 1999 Safety Evaluation Supporting Amend 131 to License NPF-30 ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205J3501999-04-0202 April 1999 Safety Evaluation Supporting Amend 130 to License NPF-30 ML20199L1361999-01-19019 January 1999 Safety Evaluation Supporting Amend 129 to License NPF-30 ML20154J5231998-10-0202 October 1998 Safety Evaluation Supporting Amend 128 to License NPF-30 ML20237C3691998-08-17017 August 1998 Safety Evaluation Supporting Amend 127 to License NPF-30 ML20217K7111998-04-23023 April 1998 Safety Evaluation Supporting Amend 126 to License NPF-30 ML20216H0651998-04-15015 April 1998 SER Approving Licensee Proposed Alternative to Use Code Case N-508-1 for Rotation of Serviced Snubbers & Prvs for Purpose of Testing in Lieu of ASME B&PV Code,Section Xi,Article IWA-7000 Requirements ML20216H4881998-04-13013 April 1998 Safety Evaluation Supporting Amend 125 to License NPF-30 ML20216C6241998-04-0202 April 1998 Safety Evaluation Supporting Amend 124 to License NPF-30 ML20217M3461998-03-25025 March 1998 Safety Evaluation Supporting Amend 123 to License NPF-30 ML20217F3181998-03-24024 March 1998 SER Accepting Relief Request for Approval for Use of Alternate Exam Requirements for Plant Inservice Insp Program ML20217F6061998-03-23023 March 1998 Safety Evaluation Supporting Amend 122 to License NPF-30 ML20216B6281998-02-24024 February 1998 Safety Evaluation Supporting Amend 121 to License NPF-30 ML20203F0841998-02-13013 February 1998 Safety Evaluation Supporting Amend 120 to License NPF-30 ML20217J9981997-10-16016 October 1997 Safety Evaluation Concluding That Proposed Transaction Will Not Affect Qualifications of UE as Holder of Plant,Unit 1 License ML20141C9031997-05-13013 May 1997 Safety Evaluation Supporting Second 10 Yr Interval ISI Program Plan Requests for Relief ISI-10 & ISI-11 ML20137Q9931997-04-0202 April 1997 Safety Evaluation Supporting Amend 119 to License NPF-30 ML20134L4421996-11-13013 November 1996 Safety Evaluation Supporting Amend 118 to License NPF-30 ML20129J3541996-10-31031 October 1996 Safety Evaluation Approving Revised Relief Request Including EN-01,EN-03,EP-02 & FC-01 Pursuant to 10CFR50.55a(f)(6)(i) ML20128N8661996-10-11011 October 1996 Safety Evaluation Approving Licensee Request to Use Code Case N-533 as Alternative to Code Requirements,Per 10CFR50.55a(a)(3) ML20129G8941996-10-0303 October 1996 Safety Evaluation Re Second 10-yr Interval Insp Program Plan Revised Request for Relief ISI-07B ML20128G0311996-10-0101 October 1996 Safety Evaluation Supporting Amend 117 to License NPF-30 ML20129G7231996-10-0101 October 1996 Safety Evaluation Supporting Amend 116 to License NPF-30 ML20115G1401996-07-15015 July 1996 Safety Evaluation Supporting Amend 114 to License NPF-30 ML20113E6631996-06-28028 June 1996 Safety Evaluation Supporting Amend 113 to License NPF-30 ML20113A5981996-06-17017 June 1996 Safety Evaluation Supporting Amend 112 to License NPF-30 ML20117J3461996-05-28028 May 1996 Safety Evaluation Supporting Amend 111 to License NPF-30 ML20111B4011996-04-30030 April 1996 Safety Evaluation Supporting Amend 109 to License NPF-30 ML20099L8921995-12-26026 December 1995 Safety Evaluation Supporting Amend 107 to License NPF-30 ML20095K3881995-12-20020 December 1995 Safety Evaluation Supporting Amend 106 to License NPF-30 ML20095E2871995-12-0707 December 1995 Safety Evaluation Supporting Amend 105 to License NPF-30 ML20094Q8681995-11-22022 November 1995 Safety Evaluation Supporting Amend 104 to License NPF-30 ML20093M0371995-10-20020 October 1995 Safety Evaluation Supporting Amend 103 to License NPF-30 ML20087L5141995-08-21021 August 1995 Safety Evaluation Supporting Amend 102 to License NPF-30 ML20086M6931995-07-20020 July 1995 Safety Evaluation Supporting Amend 101 to License NPF-30 ML20086F5531995-07-0606 July 1995 Safety Evaluation Supporting Amend 100 to License NPF-30 ML20082N8101995-04-18018 April 1995 Safety Evaluation Supporting Amend 99 to License NPF-30 ML20082C3611995-03-31031 March 1995 Safety Evaluation Supporting Amend 97 to License NPF-30 ML20082D1791995-03-30030 March 1995 Safety Evaluation Supporting Amend 96 to License NPF-30 ML20081G6641995-03-20020 March 1995 Safety Evaluation Supporting Amend 95 to License NPF-30 ML20076L0761994-10-27027 October 1994 Safety Evaluation Supporting Amend 93 to License NPF-30 ML20072S8171994-09-0606 September 1994 Safety Evaluation Supporting Amend 92 to License NPF-30 1999-09-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E2691999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities 05000483/LER-1999-006, :on 990813,inadvertent Closure of Pump Suction Valve Occurred Due to Startup FW Pump Trip.Caused by Workman Protection Assurance Program Tag Created in Error.Procedure Re Reporting Requirements Will Be Revised.With1999-09-13013 September 1999
- on 990813,inadvertent Closure of Pump Suction Valve Occurred Due to Startup FW Pump Trip.Caused by Workman Protection Assurance Program Tag Created in Error.Procedure Re Reporting Requirements Will Be Revised.With
05000483/LER-1999-005, :on 990812,operating Conditions Exceeding Previously Analyzed Values Resulted in Inoperability of Both Offsite Sources.Caused by Inadequate Acs.Changed Transformer Tap Settings.With1999-09-13013 September 1999
- on 990812,operating Conditions Exceeding Previously Analyzed Values Resulted in Inoperability of Both Offsite Sources.Caused by Inadequate Acs.Changed Transformer Tap Settings.With
05000483/LER-1999-003, :on 990811,pipe Rupture Occurred in Six Inch Drain Line Located Between D Moisture Separator Reheater First Stage Reheater Drain Tank.Caused by Flow Accelerated Corrosion.Ruptured Piping Replaced.With1999-09-10010 September 1999
- on 990811,pipe Rupture Occurred in Six Inch Drain Line Located Between D Moisture Separator Reheater First Stage Reheater Drain Tank.Caused by Flow Accelerated Corrosion.Ruptured Piping Replaced.With
05000483/LER-1999-004, :on 990808,discovered That Surveillance Test OSP-BG-V001C Did Not Adequately Test Closure of BG8497. Caused by Cognitive Personnel Error.Procedure Revised.With1999-09-0707 September 1999
- on 990808,discovered That Surveillance Test OSP-BG-V001C Did Not Adequately Test Closure of BG8497. Caused by Cognitive Personnel Error.Procedure Revised.With
ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for UE Callaway Plant,Unit 1 ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20195K3531999-06-15015 June 1999 Correction to Safety Evaluation Supporting Amend 129 to License NPF-30.Page 3 of SE Contained Editorial Error & Two Clarifications ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20195H1371999-05-28028 May 1999 Safety Evaluation Supporting Amend 133 to License NPF-30 ML20207B6181999-05-21021 May 1999 Safety Evaluation Supporting Amend 132 to License NPF-30 ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20205S1161999-04-20020 April 1999 Safety Evaluation Supporting Amend 131 to License NPF-30 ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp 05000483/LER-1999-002, :on 990309,TS Surveillance Was Missed. Caused by Misinterpretation of Surveillance Requirement. Cisa Cpis & S/G Water Level low-low Mdafp Actuation Circuits Tested Satisfactorily.With1999-04-0808 April 1999
- on 990309,TS Surveillance Was Missed. Caused by Misinterpretation of Surveillance Requirement. Cisa Cpis & S/G Water Level low-low Mdafp Actuation Circuits Tested Satisfactorily.With
ML20205J3501999-04-0202 April 1999 Safety Evaluation Supporting Amend 130 to License NPF-30 ML20205S5791999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Callaway Plant Unit 1.With ML20207A7401999-03-30030 March 1999 Draft, Evaluation of Risk of Induced Steam Generator Tube Rupture, for Callaway Plant ML20205G4071999-03-25025 March 1999 Security Event Rept:On 990304,failure to Properly Compensate for Loss of Safeguards Equipment That Could Have Resulted in Undetected Intrusion Into Protected or Vital Area,Was Discovered.Caused by Msk 325 Failure.Replaced Msk 325 05000483/LER-1999-001, :on 990119,failure to Implement Operating License Amend 106 Requirements within 30 Day Implementation Period Was Discovered.Caused by Programmatic Deficiency. Corrective Actions Implemented in Dec 1998.With1999-03-0808 March 1999
- on 990119,failure to Implement Operating License Amend 106 Requirements within 30 Day Implementation Period Was Discovered.Caused by Programmatic Deficiency. Corrective Actions Implemented in Dec 1998.With
ML20204B6741999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Callaway Plant,Unit 1.With ML20199L1361999-01-19019 January 1999 Safety Evaluation Supporting Amend 129 to License NPF-30 ML20199E7011998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Callaway Plant.With ULNRC-03990, 1998 Annual Rept for Ameren Corp/Union Electric Co. with1998-12-31031 December 1998 1998 Annual Rept for Ameren Corp/Union Electric Co. with 05000483/LER-1998-010, :on 981120,re-evaluation Determined That Addl Valves Needed to Be Included in Noted TS Requirements. Caused by New Expanded Definition of in Flow Path. TS 4.0.3 Was Entered.With1998-12-18018 December 1998
- on 981120,re-evaluation Determined That Addl Valves Needed to Be Included in Noted TS Requirements. Caused by New Expanded Definition of in Flow Path. TS 4.0.3 Was Entered.With
ML20198D9811998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Callaway Plant,Unit 1.With ML20195C8341998-11-10010 November 1998 Rev 20 to Operating QA Manual ML20195C8181998-11-0909 November 1998 Rev 19 marked-up Changes to Operating QA Manual ML20195D3581998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Callaway Plant,Unit 1.With ML20195D6931998-10-31031 October 1998 Non-proprietary Rev 3 to Electrosleeving Qualification for PWR Recirculating SG Tube Repair ML20154J5231998-10-0202 October 1998 Safety Evaluation Supporting Amend 128 to License NPF-30 05000483/LER-1998-009, :on 960830,potential for Inadequate Guidance for Safe Shutdown During Fire Requiring CR Evacuation Noted. Caused by Inadvertent Deletion of Required ACs During Procedure Rev.Revised Appropriate Procedure.With1998-09-30030 September 1998
- on 960830,potential for Inadequate Guidance for Safe Shutdown During Fire Requiring CR Evacuation Noted. Caused by Inadvertent Deletion of Required ACs During Procedure Rev.Revised Appropriate Procedure.With
ML20154L4931998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Callaway Plant Unit 1.With 05000483/LER-1998-008, :on 980814,discovered Discrepancy in Heavy Load Movement.Caused by Failure to Identify Discrepancy Between GL 81-07 Response & Plant Conditions Allowed by Tss.Will Review Plant Heavy Loads Program.With1998-09-14014 September 1998
- on 980814,discovered Discrepancy in Heavy Load Movement.Caused by Failure to Identify Discrepancy Between GL 81-07 Response & Plant Conditions Allowed by Tss.Will Review Plant Heavy Loads Program.With
ML20151Y5151998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Callaway Plant,Unit 1.With ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20237C3691998-08-17017 August 1998 Safety Evaluation Supporting Amend 127 to License NPF-30 05000483/LER-1998-007, :on 980722,noted Failure to Verify Integrity of Balancing Devices on Psvs Per TS 4.0.5.Caused by Personnel Not Being Aware That Subject Psvs Had Balancing Devices.Will Continue to Test & Refurbish Valves Offsite1998-08-17017 August 1998
- on 980722,noted Failure to Verify Integrity of Balancing Devices on Psvs Per TS 4.0.5.Caused by Personnel Not Being Aware That Subject Psvs Had Balancing Devices.Will Continue to Test & Refurbish Valves Offsite
05000483/LER-1998-006, :on 980707,RCS Pressurizer Safety Relief Valves Failed Low on as Found Set Pressure Test.Caused by Set Pressure Drift.Pressurizer SRVs Were Refurbished Following Set Pressure Testing1998-08-0606 August 1998
- on 980707,RCS Pressurizer Safety Relief Valves Failed Low on as Found Set Pressure Test.Caused by Set Pressure Drift.Pressurizer SRVs Were Refurbished Following Set Pressure Testing
ML20237B8421998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Callaway Plant,Unit 1 ML20236Q9991998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Callaway Plant,Unit 1 1999-09-07
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SAFETY EVALVATION BY ThE OFFICE OF NUCLEAR REACTOR REGULATION RELAT[D TO AMENDMINT NO. 60 TO FACILITY OFUiKTING LICTIST~RD~~IFT-30 UNION ELECTRIC COMPANf CALLAWAY PLANT, UNIT 1
~MCIET NO. hTN 50 4lG
1.0 INTRODUCTION
In its letter dated March 15, 1991, as supplemented by letters dated August 15, 1991 and January 23, 1992, the Union Electric Company (the licensee) requested a revision to Technical Specification 3.4.6.2.f and the associated Bases for the Callaway Plant, Unit 1.
The proposed revision would replace the present maximum allowable leakage rate of 1-gallon per minute (
any of the reactor Coolant system presture isolation valves (PlVs) gpm) from specified in Table 3.4-1 of the Callaway Tecanical Specifications (TSs).
This new set of maximum allowable leakage rates would be dependent on the size of the P!Vs. The proposed maximum allowable leakage of these P!Vs would be limited to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm.
Additionally, the licensee proposed in its application cited above that Table 3.4-1 be expanded to provided a more detailed description of the 35 affected PlVs and to correct some valve identification numbers and descriptions.
2.0 EVALUATION The subject TS (i.e., TS 3.4.6.2) establishes six separate criteria of reactor coolant system (RCS) maximum allowable leakage rates. One of these is the maximum allowable leakage rate from the RCS PlVs which are presently limited to 1 gpm for each PlV (TS 3.4.6.2.f).
The licensee proposed that this single value be replaced by limiting leakage rates dependent on the nominal diameter of the PlYs.
Specifically, the licensee has proposed that the maximum allowable leakage rate for the 35 P!Vs listed in Table 3.4-1 of the Callaway TSs be established as 0.5 gpm per nominal inch of valve size up to a maximum value of 5 gpm at an RCS pressure of 2235 t20 pounds per square inch gauge (psig).
The present value of the maximum allowable leakage iate of 1 gpm for each PlV, independent of size, is arbitrary in that this TS limit does not recognize that leakage through check valves tends to be larger as valve size increases.
(This is related to the leakage area being proportional to the valve diameter.)
As a result, this use of a single, relatively low limiting value of PlV leakage for the larger valves requires them to be reworked for the same limiting leaka? rate as that for a small PlV.
However, a measured leakage rate of 1 gpm from a 2-inch Ply is more significant than a leakage of 1 gpm from a 10-inch PIV in that it is indicative of greater degradation.
9202040378 920124 PDR ADOCK 05000483 P
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. The net result is that the larger PlVs will tend tr be reworked more frequently t' an justified, considering the signifi:ance of the 1 gpm leakage through these larger valves. The licensee 's proposal, to the extent that it reduces excessive reworking of the larger PlVs will thereby reduce radiation exposure to the plant operating personnel.
The licensee's proposal to revise the 1e'akage limit for the PlVs in TS Table 3.4 1 introduces a more rational correlation between the size of a Ply and its limiting leakage rate.
Inasmuch as thin proposed revision does not change the limits on identified or unidentified leakage from the RCS, there will be no significant increase in the total leakage outside the reactor priniary containment and no significant increase in the amount of radioactivity released to the environment under normal or accident conditions.
The proposed change will allow operaticn with sone increase in the leakage from certain PlVs, however plant operation will continue to be restricted by the TS limits on total leakage. The slight increase in allowable leakage from individual PlVs is still sufficiently conservative to permit the identification of significant valve degradttion. Additionally, the Bases section is revised to delete the specific reference to 1 gpm leakage for any RCS pressure isolation valve, consistent with the proposed change to TS 3.4.6.2.f.
The licensee stated in its supplemental letter dated August 15,1991 that there is more than sufficient pressure relief capacity downstream of the PIVs to prevent overpressurization of piping and equipment as a result of the proposed higher limiting leakage rates.
Based or discussions with N staff, the licensee revised its original request on January 23.195"'
The revised request changed the leakage limit for va hes which are 2-inche u smaller to 0.5 gpm per nominal inch of valve size. This change is consistent with the Standard Technical Specifications. The revised limits are more conservative than those originally proposed by the licensee and therefore, this revision does not alter the staff's original proposed no significant hazards determination.
Accordingly, the NRC staff finds the licensee's proposal acceptable on the basis that it will tend to decrease radiation exposure to plant operating personr4 and will allow continued plant operation without a significant increase in the resulting leakage frcm the reactor primary containment.
The staff concludes, therefore, that there is no significant increased risk to public health and safety.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Missouri State official was notified of the proposed issuance of the amendment.
The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the instal-lation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves rc 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 cumula ve occupational radiation exposure.
The Commission has previously issued a pr'un -
finding that this amendment involves no significant hazar i ',;iderat, and there bas been no public comment on such finding (56 FR 24220).
Accordingly, this amendment meets 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 issu.ce of this amendment.
5.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safet be endangered by operation in the proposed nanner, (2) y of the public will not such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
M. D. Lynch Date:
January 24, 1992
.