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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML20216F1381999-09-0808 September 1999 Forwards Retake Exam Repts 50-280/99-302 & 50-281/99-302 on 990824.One SRO Applicant Who Received re-take Operating Test Passed re-take Exam ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152A4741999-05-19019 May 1999 Forwards Completed Registration Form for Renewal of ASTs at Surry Nuclear Power Station,Iaw Section 9VAC 25-91-100.F ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML20217D6621999-05-14014 May 1999 Forwards NRC Operator Licensing Exams 50-280/99-301 & 50-281/99-301 (Including Completed & Graded Exams) for Tests Administered on 990329-0401 & 990412-15.Nine Candidates Passed (& One Failed) Exam ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18152B3571999-10-22022 October 1999 Requests Relief from Temporary Repair of Through Wall Leak Discovered on 30 Inch Component Cooling Heat Exchanger Discharge Pipe Associated with Service Water Sys Common to Surry Units 1 & 2 ML18152B3581999-10-14014 October 1999 Submits Response to Violations Noted in Insp Repts 50-280/98-201 & 50-281/98-201.Corrective Actions:Visual Insps Were Completed on Accessible Coatings Inside Containment for Both Units 1 & 2 ML18152B3541999-10-12012 October 1999 Requests Use of Code Case N-532 & N-619,per Provisions of 10CFR50.55a(a)(3).Detailed Info Supporting Request,Encl. Attachment 2 Includes Technical White Paper That Provides Further Technical Info ML18152B3391999-09-27027 September 1999 Forwards Revised Relief Request IWE-3,which Now Includes Addl Visual Exam Requirement After post-repair or Mod Pressure Testing Is Completed,Per Telcon with NRC ML18152B3401999-09-27027 September 1999 Requests That Ma Walker Be Removed from List of Individuals Scheduled to Take Exam IAW Guidance Provided in NUREG-1021, Operator Licensing Exam Stds for Power Reactors ML18152B3381999-09-21021 September 1999 Forwards in Triplicate,Applications for Renewal of License for Bf Jurewicz & JW Heide.Without Encls ML18152B3331999-09-17017 September 1999 Forwards Revised 180-day Response to NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. ML18152B6671999-09-17017 September 1999 Forwards Two NRC Forms 536,containing Info on Proposed Site Specific Operator Licensing Exam Schedules & Estimated Number of Applicants Planning to Take Exams And/Or Gfes,In Response to NRC Administrative Ltr 99-03 ML18152B3341999-09-16016 September 1999 Requests Relief from Specific Requirements of Subsection IWE of 1992 Edition with 1992 Addenda of ASME Section XI Re Containment Liner Examination Requirements,For North Anna & Surry Power Stations ML18152B4521999-09-14014 September 1999 Forwards Comments on Review of Preliminary Accident Sequence Precursor Analysis of Operational Event That Occurred at Plant,On 980508,as Reported in LER 98-009 ML18152B4501999-09-0808 September 1999 Submits in Triplicate,Application for Renewal of License for Rd Scherer,Iaw 10CFR55.57.Requests That Certification of Medical Exam by Facility Licensee,Nrc Form 396,be Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4471999-09-0101 September 1999 Requests That NRC Remove Listed Labels from Distribution ML18152B3711999-08-27027 August 1999 Forwards LER 99-005-00,per Plant TS Table 3.7.6.Rept Has Been Reviewed by Station Nuclear Safety & Operating Committee.Commitment Made by Util,Listed ML18152B3851999-08-23023 August 1999 Forwards Revised TS Basis Pages for TS 3.1.B,deleting Reactor Vessel Toughness Data Duplicated in Ufsar.Ref to Applicable UFSAR Section Included in TS Basis ML18152B3651999-08-20020 August 1999 Requests Removal of License Condition from Sh Wightman Operator License SOP-21538.Updated NRC Form 396 Is Encl.Form NRC 396 Withheld,Per 10CFR2.790(a)(6) ML18152B3681999-08-20020 August 1999 Submits 30-day Rept Re Two Instances in Which Conditions of Approval in Coc Were Not Observed in Making Shipment.Two Type B Shipments Using Model CNS 8-120B Package Were Made After Expiration of QA Program Approval Between 990531-0628 ML18152B3661999-08-20020 August 1999 Provides Medical Status Rept for E Washington,As Required by License Conditions.Summary of E Washington Current Physical Exam & Pertinent Lab Data Attached.Encl Withheld,Per 10CFR2.790(a)(6) ML18152B3801999-08-18018 August 1999 Forwards Technical Rept NE-1206,Rev 0, Surry Unit 2,Cycle 16 Startup Physics Tests Rept, Summarizing Results of Physics Testing Program Performed After Initial Criticality on 990525 ML18152B3781999-08-13013 August 1999 Forwards ISI Summary Rept for Surry Power Station,Unit 2 for 1999 Refueling Outage.Rept Provides Summary of Examination Performed During Outage for Third ISI Interval.No New Commitments Were Made ML18152B3751999-08-13013 August 1999 Forwards LER 99-004-00,IAW 10CFR50.73.Commitment Made by Util,Listed ML18152B4081999-08-0606 August 1999 Forwards Response to NRC 990520 & 0525 RAIs Re North Anna & Surry Responses to GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves. ML20210Q7661999-08-0606 August 1999 Requests Exception to 10CFR50.4 Requirement to Provide Total of Twelve Paper Copies When Submitting Surry & North Anna UFSAR Updates.Seek Approval to Submit Only Signed Original & One CD-ROM Version,Per Conversation with J Skoczlas ML18152B4091999-08-0505 August 1999 Forwards Vepc semi-annual fitness-for-duty Program Performance Data Rept for 990101-990630,IAW 10CFR26.71(d) ML18152B4001999-07-29029 July 1999 Requests Relief from Certain Impractical Requirements of ASME Section XI Code Associated with Partial Exams Conducted During 1998 Surry Unit 1 Refueling Outage.Relief Request SR-020 Encl ML18152B3981999-07-28028 July 1999 Forwards 60-day Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Commitments Contained in Ltr,Listed ML18152B3971999-07-26026 July 1999 Provides Estimates of Licensing Actions Expected to Be Submitted in Fys 2000 & 2001,in Response to NRC AL 99-02 ML18151A6281999-07-23023 July 1999 Forwards Revised Epips,Including Rev 19 to EPIP-4.02,rev 14 to EPIP-4.16,rev 8 to EPIP-4.21 & Rev 7 to EPIP-4.30.EP & EPIPs Continue to Meet Stds of 10CFR50.47(b) ML18152B3991999-07-23023 July 1999 Requests That License for Jz Laplante Be Canceled as License Is No Longer Required ML18152B3961999-07-23023 July 1999 Forwards Preliminary,Uncertified License Application & Medical Certification for License to Operate Surry Power Station Units 1 & 2 for Ds Cobb.Encl Withheld,Per 10CFR2.790 (a)(6) ML18152B3931999-07-16016 July 1999 Forwards Updated NRC Form 396 & Ltr,Which Documents Medical Status of Mb Gross,License SOP-20476-2.Encl Withheld from Public Disclosure,Per 10CFR2.790(a)(6) ML18152B4401999-07-0101 July 1999 Informs NRC That on 990511,Dominion Resources,Inc,Executed Amended & Restated Agreement & Plan of Merger with Consolidated Natural Gas Co ML18152B4371999-06-24024 June 1999 Forwards Response to NRC Request for Clarification of Relief Requests Submitted on 990212,requesting Relief from Performing Hydrostatic Testing for Certain Small Diameter Class 1,RCS Pressure Boundary Connections ML18152B4361999-06-22022 June 1999 Forwards Response to RAI Re Surry & North Anna Power Stations,Units 1 & 2,per GL 96-06 ML18152B4301999-06-0303 June 1999 Informs of Util Intention to Revise Schedule for Submittal of License Renewal Applications for Surry & North Anna Power Stations to March 2002 ML18152B4261999-05-28028 May 1999 Provides Formal Notification of Effect of Recent Organizational Restructuring on OLs of North Anna & Surry Power Stations,Per NRC 990513 Telcon Request ML18152B4221999-05-27027 May 1999 Forwards Info Concerning Changes to ECCS Evaluation Models & Application in Existing Licensing Analyses for Surry & North Anna Power Stations,Units 1 & 2 ML18152B4231999-05-26026 May 1999 Informs That Vepc Will Revise 180 Day Response to NRC GL 96-05,within 120 Days of Date of Ltr to Incorporate Commitment to Participate in Joint Owners Group Program as Applicable ML18152B4211999-05-25025 May 1999 Forwards Rev 1 to Relief Request P-11 to Clarify Original Intent of Request by Specifically Requesting Relief from Requirements of Section 6.1 of OM-6 ML18152B4171999-05-17017 May 1999 Provides Notification of Number of Steam Generator Tubes That Were Plugged During Spring 1999 Refueling Outage Planned ISI ML18152A3701999-05-13013 May 1999 Submits Proposal to Use Provisions of ASME Section XI Code Case N-597 for Analytical Evaluation of Class 1,2 & 3 Carbon & Low Alloy Steel Piping Components Subjected to Wall Thinning as Result of Flow Accelerated or Other Corrosion ML18152B4121999-05-0303 May 1999 Forwards Application for Renewal of License for SV Ross. Encl Withheld Per 10CFR2.790(a)(6) ML18152B4101999-04-29029 April 1999 Forwards Scope & Objectives for 990803 Surry Power Station Emergency Exercise.Without Encls ML18152B6561999-04-23023 April 1999 Forwards Annual Radioactive Effluent Release Rept for Surry Power Station,Jan-Dec 1998, Which Includes Summary of Quantities of Radioactive Liquid & Gaseous Effluents & Solid Waste Released During CY98 ML18152B6491999-04-13013 April 1999 Forwards MOR for Mar 1999 for Surry Power Station,Units 1 & 2.MOR for Feb 1999 Incorrectly Stated Gross Electrical Energy Generated (Mwh) for Unit 2.Rept Should Have Stated Monthly Figure as 568965.0 ML18151A5851999-03-31031 March 1999 Forwards Rept on Status of Decommissioning Funding for Each of Four Nuclear Power Reactors,Per 10CFR50.75(f)(1) ML18152A2801999-03-30030 March 1999 Forwards Summary of Structural Integrity Evaluation of Thermally Induced Over Pressurization of Containment Penetration Piping During DBA for SPS & Naps,Units 1 & 2,per GL 96-06.Draft Proposed UFSAR Revised Pages,Encl ML18153A2721999-03-29029 March 1999 Forwards LER 99-002-00 Per 10CFR50.73.Listed Commitments Contained in Ltr ML18153A3421999-03-26026 March 1999 Provides Updated Medical Status Rept for Wb Gross in Accordance with License SOP-20476-02,Docket 55-5228,as Amended by 980320 License Amend.Informs That Gross Exhibits No Performance Problems & Will Continue on Current Medicine ML20204H0331999-03-17017 March 1999 Forwards Rev 5 to PSP for Surry & North Anna Power Stations & Associated Isfsis.Description & Justification for Changes Included with Plan Rev.Rev 5 to PSP Withheld Per 10CFR73.21 ML18153A3411999-03-15015 March 1999 Forwards Signed Applications & Medical Certificates for Initial License at Surry Power Station Units 1 & 2 for Listed Individuals.Without Encls 1999-09-08
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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 April 22, 1998 United States Nuclear Regulatory Commission Serial No.98-157 Attention: Document Control Desk NS&L/BAG Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 ANNUAL REACTOR COOLANT SPECIFIC ACTIVITY REPORT Pursuant to the reporting requirements of Surry Technical Specification 6.6.A.2.b, Virginia Electric and Power Company submits the annual report of reactor coolant specific activity analysis for 1997. This report provides the results of specific activity analysis in which the limits of Surry Technical Specification 3.1.D.4 were exceeded.
The specific activity of the reactor coolant for Unit 1 exceeded 1.0 µCi/cc DOSE EQUIVALENT 1-131 during three events for the reporting period, but remained below the 100/E µCi/cc limit. Information required by Surry Technical Specification 3.1.D.4 when the specific activity exceeds the specified limit is provided in the attachment.
The specific activity of the reactor coolant for Unit 2 did not exceed 1.0 µCi/cc dose equivalent 1-131 or 100/E µCi/cc during the calendar year 1997 and therefore no additional information is required for the annual report.
Please contact us if you have any questions or require additional information.
Very truly yours, D. A. Christian Site Vice President Attachment Commitments made in this letter: None
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9804280041 980422 PDR ADOCK 05000280 p PDR
cc: United States Nuer Regulatory Commission Region II Atlanta Federal Center
,61 Forsyth Street, S. W., Suite 23T85
- Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station
e e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 1 of 5 UNIT 1 REACTOR COOLANT SPECIFIC ACTIVITY IN EXCESS OF TECHNICAL SPECIFICATION 3.1.D.4 This report is submitted in accordance with Surry Power Station Technical Specification 6.6.A.2.b, which requires submission of an annual report with detailed information when specific activity of the reactor coolant system (RCS) exceeds 1.0 µCi/cc dose equivalent 1-131 or 100/E µCi/cc.
A. On January 24, 1997, at 0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 2. 73E+O µCi/cc when the unit was at 0%
power. A sample at 100% reactor power taken prior to power reduction was 3.55E-2 µCi/cc 1-131 dose equivalent. The high iodine dose equivalent level was caused by fuel cladding defects and ramping the unit offline for a Maintenance outage.
Operations personnel entered the following Technical Specification (TS) 3.1.D.3 action statement:
"With the specific activity of the reactor coolant greater than 1.0 µCi/cc dose equivalent 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding 10.0 µCi/cc 1-131 dose equivalent level, the reactor shall be shut down and cooled to 500 °For less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after detection."
Appropriate RCS sampling and analysis continued and at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> on January 24, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.
The following information is provided in accordance with the requirements of TS 3.1.D.4:
- 1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:
Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 1/22/97 0800 100 % 110 No 1/22/97 0903 100 % 110 No 3.55 E-2 1/23/97 0800 100 % 110 No 1/24/97 0100 100 % 110 No 1/24/97 0200 93% 110 No 1/24/97 0500 42% 110 No 1/24/97 0555 30% 110 No 6.87 E-2 1/24/97 0700 15% 110 No 1/24/97 0800 0% 110 No 1/24/97 0810 0% 110 No 2.73 E+O
e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 2 of 5
- 2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 1/24/97 0555 3.91E-2 6.17E-2 7.82E-2 2.56E-2 6.93E-2 6.87E-2 1/24/97 0810 2.07E+O 9.08E-1 2.01E+O ::;;1.20E-1 9.92E-1 2.73E+O 1/24/97 1025 1.61E+O 4.09E-1 1.57E+O 2.54E-2 6.47E-1 2.10E+O 1/24/97 1240 1.58E+O 2.96E-1 1.25E+O ::;;2.62E-2 4.58E-1 1.97E+O 1/24/97 1445 1;37E+O 2.43E-1 9.84E-1 ::;;1.48E-2 3.13E-1 1.67E+O 1/24/97 1635 1.11 E+O 1.92E-1 7.90E-1 ::;;4.31 E-3 2.17E-1 1.35E+O 1/24/97 1845 8.79E-1 1.74E-1 5.65E-1 ::;;4. 71 E-3 1.35E-1 1.05E+O 1/24/97 2045 7.12E-1 1.64E-1 4.45E-1 ::;;3.22E-3 9.28E-2 8.46E-1
- 3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
10 120
-*-%Power 100 1
\ 80 c.)
\ .
GI g \ 60 3:
0 0 D.
\ ~
0 0.1 40 20 0.01 0 1/20/97 1/22/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 1/24/97 0105 0903 0555 0810 1025 1240 1445 . 1635 1845 2045
- e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 3 of 5 B. On February 20, 1997, at 0112 hours0.0013 days <br />0.0311 hours <br />1.851852e-4 weeks <br />4.2616e-5 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 1.14E+O µCi/cc when the unit was at 0%
power. A sample at 100% reactor power taken prior to power reduction was 8.53E-2 µCi/cc 1-131 dose equivalent. The high iodine dose equivalent level was caused by fuel cladding defects and from manual trip of the unit from 53% reactor power at 2259 hours0.0261 days <br />0.628 hours <br />0.00374 weeks <br />8.595495e-4 months <br /> on February 19, 1997. Operations personnel entered the action statement in Technical Specification (TS) 3.1.D.3. Appropriate RCS sampling and analysis continued and at 0519 hours0.00601 days <br />0.144 hours <br />8.581349e-4 weeks <br />1.974795e-4 months <br /> on February 20, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.
The following information is provided in accordance with the requirements of TS 3.1.D.4:
- 1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:
Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 2/18/97 0100 100% 110 No 2/19/97 0050 100% 110 No 8.53 E-2 2/19/97 0100 100% 110 No 2/19/97 2200 91 % 104* No 2/19/97 2259 53% 104* No 2/20/97 0112 0% 104* No 1.14 E+O 2/20/97 0316 0% 109 No 1.11 E+O 2/20/97 0519 0% 109 No 1.00 E+O
- 2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 2/19/97 0050 3.86E-2 8.78E-2 1.16E-1 1.13E-1 1.23E-1 8.53E-2 2/20/97 0112 7.21 E-1 5.12E-1 1.24E+O 9.05E-2 6.98E-1 1.14E+O 2/20/97 0316 7.62E-1 2.87E-1 1.06E+O 1.71 E-2 5.44E-1 1.11 E+O 2/20/97 0519 7.09E-1 2.04E-1 9.37E-1 ~8.94E-3 4.08E-1 1.00E+O 2/20/97 0727 6.01 E-1 1.38E-1 7.38E-1 ~5.68E-3 2.66E-1 8.28E-1
e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 4 of 5
- 3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
10 120
~- ..... - '\
-A-% Power 100
\
1 80
...GI
-u u
u:l 60
~
0
==
0 C.
0.1 40 2/17/97 2/18/97 2/19/97 2/20/97 2/20/97 2/20/97 2/20/97 2/20/97 0025 1255 0050 0112 0316 0519 0727 0935 C. On March 7, 1997, at 0505 hours0.00584 days <br />0.14 hours <br />8.349868e-4 weeks <br />1.921525e-4 months <br />, the Unit 1 RCS was sampled and the 1-131 dose equivalent was determined to be 1.05E+O µCi/cc when the unit was at 0% power. A sample at 96% reactor power taken prior to power reduction was 7.28E-2 µCi/cc.
The high iodine dose equivalent level was caused by fuel cladding defects and from ramping the unit offline at 0349 hours0.00404 days <br />0.0969 hours <br />5.770503e-4 weeks <br />1.327945e-4 months <br /> on March 7, 1997 for a refueling outage. The fuel containing cladding defects was removed from the core. Operations personnel entered the action statement in Technical Specification (TS) 3.1.D.3. Appropriate RCS sampling and analysis continued and at 0838 hours0.0097 days <br />0.233 hours <br />0.00139 weeks <br />3.18859e-4 months <br /> on March 7, 1997, the RCS 1-131 dose equivalent specific activity was restored within limits.
The following information is provided in accordance with the requirements of TS 3.1.D.4:
- 1. Reactor power history, clean-up system flow history, history of degassing operations, and 1-131 dose equivalent specific activity starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded:
e Docket Nos: 50-280 Serial No.98-157 Attachment 1 Page 5 of 5
' )
Date Time Power Letdown Degassing 1-131 DE Flow (gpm) Operations (µCi/cc) 3/05/97 0010 95% 110 No 7.28E-2 3/05/97 0500 95% 110 No 3/06/97 0500 94% 110 No 3/07/97 0100 53% 110 No 3/07/97 0415 0% 110 No 8.80E-1 3/07/97 0505. 0% 110 No 1.05E+O 3/07/97 0645 0% 110 No 1.07E+O 3/07/97 0838 0% 110* No 9.41 E-1
- 2. Isotopic analysis for radioiodine performed prior to exceeding the limit, results of the analysis while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
Date Time 1-131 1-132 1-133 1-134 1-135 1-131 DE 3/07/97 0415 5.89E-1 4.53E-1 8.77E-1 4.37E-2 4.54E-1 8.80E-1 3/07/97 0505 7.17E-1 4.44E-1 1.02E+O 3.12E-2 4.81 E-1 1.05E+O 3/07/97 0645 7.50E-1 3.16E-1 9.85E-1 ~1.15E-2 3.91 E-1 1.07E+O 3/07/97 0838 6.96E-1 1.88E-1 7.97E-1 4.05E-3 '2.80E-1 9.41 E-1
- 3. Graph of the iodine-131 and iodine-133 activity analysis performed prior to exceeding the limit, results while the limit was exceeded, and results of one analysis after the radioiodine activity was reduced to less than the limit:
120
-A-%Power 100 80
...CD 60 0 C.
40 3/03/97 3/05/97 3/07/97 3/07/97 3/07/97 3/07/97 3/07/97 3/07/97 0415 0010 0415 0505 0645 0838 0917 1300