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| {{Adams | | {{Adams |
| | number = ML20214J915 | | | number = ML20236K439 |
| | issue date = 05/11/1987 | | | issue date = 08/04/1987 |
| | title = Insp Rept 50-382/86-34 on 861208-11 & 870330-0401.Violation Noted:Local Leak Rates for Six Valves Tested Recorded as off-scale W/No Recorded Value | | | title = Ack Receipt of 870618 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/86-34 |
| | author name = Hunnicutt D, Ireland R, Tapia J | | | author name = Gagliardo J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Dewease J |
| | addressee affiliation = | | | addressee affiliation = LOUISIANA POWER & LIGHT CO. |
| | docket = 05000382 | | | docket = 05000382 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-382-86-34, NUDOCS 8705280250 | | | document report number = NUDOCS 8708070120 |
| | package number = ML20214J884
| | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | page count = 2 |
| | page count = 3 | |
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| | .*'s In Reply Refer To: |
| l APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION
| | Docket: 50-382/86-34 |
| | $1W Louisiana Power & Light Company ATTN: J. G. Dewease, Senior Vice President Nuclear Operations 317 Baronne Street New Orleans, Louisiana 70160 Gentlemen: |
| | Thank you for your letter of June 18, 1987, in response to our letter and Notice of Violation dated May 19, 198 We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
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| ==REGION IV==
| | Sincerely, |
| NRC Inspection Report: 50-382/86-34 License: NPF-26 Docket: 50-382 Licen:,ee: Louisiana Power and Light Company (LP&L)
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| 142 Delaronde Street New Orleans,' Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection At: Taft, Louisiana Inspection Conducted: December 8-11, 1986, and March 30 through April 1, 1987
| | * :ct Signed by; WLU J. E. Gagliardo, Chief Reactor Projects Branch cc: |
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| | Louisiana Power & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: N. S. Carns, Plant Manager P. O. Box B Killona, Louisiana 70066 Middle South Services ATTN: Mr. R. T. Lally P. O. Box 61000 New Orleans, Louisiana 70161 f' |
| Inspector: f.o d 5 f 6 f Bb Date'
| | RIV:RSB/0S Tapia:gb 05 @ |
| J. Jr.Japia, Operagns Section, Reactor
| | DMHunnicutt lRPB/A JJaudon RSBh*, |
| | TFWesterman RPB JEGagliardo 6/Q/87 '5 / 4 /87 g/f/87 9/1/87 pf/87 870BO70120 870004 PDR G |
| | ADOCK 05000382 PDR |
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| S Wety Branch Reviewed: . I9 k bo-p6 D. M. Hunnicutt, Chief, Operations Section 5/4/f7 D&te'
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| Reactor Safety Branch Approved: [ d. C- @///F'7 R. E. Ireland; Acting Chief, Operations Date Section, Reactor Safety Branch Inspection Summary Inspection Conducted December 8-11, 1986, and March 30 through April 1, 1987 (Report 50-382/86-34) +
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| Areas Inspected: Routine, unannounced inspection of the Local Leak Rate Testing Progra Results: Within the one area inspected, one violation was identifie '
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| 8705280250 870519 PDR ADOCK 05000302 G PDR
| | Louisiana Power & Light Company 2 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Safety and Regulatory Affairs Manager 317 Baronne Street P. 0. Box 60340 New Orleans, Louisiana 70160 Louisiana Radiation Control Program Director bec to DMB (IE01) |
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| | bec distrib. by RIV: |
| | *RPB *D. Weiss, RM/ALF |
| | *RRI R. D., Martin, RA |
| | *Section Chief (RPB/A) DRSP RPSB *RSB |
| | * MIS System * Project Inspector, RPB |
| | *RSTS Operator *R. Hall |
| | *RIV File *J. Wilson, NRR Project Manager J. Tapia SectionChief(RSB/05) |
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| | LOUISI& AN POWER A LIGHT / 317NEW BARONNESTREET * P. O. BOX 60340 ORLEANS, LOUISIANA 70160 + (504) 595-3100 |
| DETAILS 1. Persons Contacted T. F. Gerrets, Nuclear QA Manager R. F. Buski, Engineering Manager N. S. Carns, Plant Manager D. Schultz, Shift Technical Advisor (STA), Supervisor R. Peters, STA K. Brewster, Licensing G. Forgala, Shift Supervisor 2. Containment Local Leak Rate Testing Program Implementation of the ongoing containment local leak rate test (LLRT)
| | $@i?O sYsVIO June 18, 1987 W3P87-1700 A4.05 QA U.S. Nuclear Regulatory Commission I IN@[5IlV//: |
| program was addressed during an inspection conducted on December 8-11, 1986. Subsequent to that inspection, the NRC inspector performed an in-office review of all local leak rate test data and applicable Condition Identification Work Authorization LP&L Surveillance Procedure No. PE-5-002, Revision 3, " Local Leak Rate Test," was reviewed by the NRC inspector to verify compliance with the specified test requirements and acceptance criteria contained in 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testin for Water Cooled Power Reactors," and in Section 3/4.6.1 of the plant Technical Specification The review provided verification that the following test attributes were correctly addressed: All applicable penetration boundaries and isolation valves were subjected to local leak rate testin Local leak rate tests were performed at peak accident pressur The local leak rate test program utilized an approved method for testin Penetration leakage rates were determined using the maximum pathway leakage, Criteria and response were specified for local leak rate test and combined leakage rate failure, Criteria and response were specified for the failure of components specifically cited in the Technical Specification The instrument calibration certifications traceable to the U.S. National Bureau of Standards for four rotometers, one pressure and one temperature
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| | ATTN: Document Control Desk 'I f |
| | Washington, D.C. 20555 j M l 9 lg8'[ |
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| | w Subject: Waterford 3 SES l Docket No. 50-382 - |
| | License No. NPF-38 NRC Inspection Report 86-34 Attached is the Louisiana Power and Light Company (LP&L) response to l Violation No. 8634-01 identified in Inspection Report No. 86-3 If you have any questions on the response, please contact G.E. Wuller, Operational Licensing, at (504) 464-349 Very tr y yours, jk Ye .v |
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| | K.W. [ook Nuclear Safety and Regulatory Affairs Manager KWC:PTM:pmb Attachment cc: R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office E.L. Blake W.M. Stevenson 54 ~ |
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| | ( "AN EQUAL OPPORTUNITY EMPLOYER" fc41 1%i |
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| | #, o Attachnsnt to W3P87-1700 Sheet 1 of 2 LP&L Response to Violation No. 8634-01 VIOLATION NO. 8634-01 Failure to Quantify Containment Isolation Valve Leakage The requirements of Appendix J to 10CFR Part 50.54(o), are invoked as a condition of the license for all water cooled power reactors. Appendix J requires that a continuous running tum of local leak rates for penetrations and isolation valves subjected to this testing not exceed 0.6 times the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant acciden Contrary to the above, it was found during the week of December 8-11, 1986 that the local leak rates for six valves required to be tested had recorded as-found leak results of "off-scale" with no recorded value, so that the continuous running sum of local leak rates was not known and the required comparison with the Appendix J criterion could not be made for the as-found conditio This is a Severity Level IV violatio RESPONSE (1) Reason for the Violation The requirements of Appendix J Section III.C.3 to 10CFR Part 50 as invoked through Part 50.54(o) states in part: "The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La." At the time the local leak rate testing was being performed the plant was in Mode As the result of local leak rate testing, six valves had as-found leak rates which exceeded the capability of the test equipmen The data as recorded was identified as "off scale" with no numerical value identified. During this inspection the NRC inspector noted that because of the recorded values of "off scale" he was unable to ascertain if the criterion of 0.60 La for leakage was satisfie (2) Corrective Action That Has Been Taken Prior to performing maintenance on the six valves the local leak rate test configuration was modified to provide a greater flow measuring capability. Of the six valves identified as having leak rates of "off scale", numerical values were identified for 5 of these valves. The sixth valve, a 24 inch contc1nment vacuum check valve (CVR-102) could not be pressurized with the modified test unit, thus r.o leak rate could be establishe Correctiva action was initiated by maintenance on all six valves and the appropriate retests were conducted. Acceptable leak rates were . |
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| | identified for these valves prior to returning to Mode 4. In accordance with the Appendix J criterion the required comparison for |
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| gauge used in the local leak rate testing program were reviewed by the NRC inspector. Three local leak rate tests performed on three valves were witnessed by the NRC inspector to determine if the licensee was properly complying with regulatory and procedural commitment The continuous running sum of local leak rates for all penetrations and isolation valves required to be subjected to local leakage rate testing is required by 10 CFR Part 50, Appendix J, to be less than 0.60 La, where La is the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant accident (Pa). With an La value of 0.5 percent per 24 hours by weight at 44 psig, 0.6 La equates to 63,070 cc/ min. The method used to obtain the continuous running sum of local leak rates is to add the new test results and subtract the previous results for the same penetrations and isolation valves tested to the combined local leak rate sum. The NRC inspector reviewed the local leak rate data sheets to determine if the sum of the local leak rates for all boundaries and valves suoject to local leak rate testing met the acceptance criteri From a review of the local leak rate data sheets, it was determined that six valves had recorded as-found results of "off-scale" with no value entered. The required comparison with the Appendix J requirement of 0.6 La could therefore not be made for the as-found condition. This is an apparent violation (382/8634-01) of the above requiremen . Exit Interview The NRC inspector met licensee representatives and the resident inspector at the conclusion of the inspection on Decembu 11, 1986. The NRC inspector informed the licensee of the apparent violation and also informed the licensee that additional in-office review would be required prior to its issuance.
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| | #'# Attachment to W3P87-1700 Sheet 2 'f 2 the as-found condition could not be made for CVR-10 For the purpose of this test it was assumed that the leakage for CVR-102 wculd result in exceeding the 0.60 La limi As per Appendix J Section V. requirements this valve will be reported in a separate accompanying summary report to the " Reactor Containment Building Integrated Leak Rate Test" repor The ability to indicate and quantify leakage ratea has been increased to account for valves with larger leak rate A continuous running sum total leak rate has been established to be able to, at any time, identify present leakage as compared to the 0.60 La limi It is conceivable in the future that a gross leskage may exceed the capability of our test uni In this event, alternative test methods or evaluations will be conducted to determine whether the 0.60 La criteria for Type C testing is met and a summary report will be prepared in accordance with Appendix J Section V. (3) Corrective Action To Be Taken Surveillance Procedure (PE-5-002) " Local Leak Rate Test (LLRT)" will be modified to maintain a continuous running sum of leak rates that fall within the 0.60 La criteria. Failed valves will be reworked and retested to ensure the total leakage is less than 0.60 La prior to entering a mode where the requirement exist (4) Date When Full Compliance Will Be Achieved Changes to the surveillance Procedure " Local Leak Rate Test (LLRT) are expected to be complete by July 15, 198 . |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L0421999-10-21021 October 1999
Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20217N2111999-10-19019 October 1999
Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings
ML20217L0101999-10-18018 October 1999
Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions
ML20217L0141999-10-18018 October 1999
Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator
ML20217G7051999-10-14014 October 1999
Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004
05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999
Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal
ML20217D5151999-10-0707 October 1999
Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls
ML20217C6251999-10-0505 October 1999
Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives
ML20212J6921999-09-29029 September 1999
Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified
ML20216G2441999-09-27027 September 1999
Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted
05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999
Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form
IR 05000382/19993011999-09-21021 September 1999
Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14
ML20212D8761999-09-16016 September 1999
Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl
ML20212C2471999-09-16016 September 1999
Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld
ML20212C2391999-09-16016 September 1999
Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901
ML20212C5881999-09-14014 September 1999
Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted
ML20211Q4421999-09-0909 September 1999
Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations
ML20211P4121999-09-0707 September 1999
Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d)
ML20211M8391999-09-0303 September 1999
Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl
ML20211L3681999-09-0202 September 1999
Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld
ML20211K9741999-09-0101 September 1999
Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy
05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999
Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form
ML20211M3641999-08-30030 August 1999
Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld
ML20211G5751999-08-27027 August 1999
Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4
ML20211E3281999-08-26026 August 1999
Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments
05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999
Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately
05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999
Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form
ML20211F5421999-08-24024 August 1999
Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed
ML20211F3561999-08-24024 August 1999
Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable
ML20211F4611999-08-24024 August 1999
Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements
ML20211G1731999-08-23023 August 1999
Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20211C5101999-08-19019 August 1999
Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15
ML20210T9791999-08-18018 August 1999
Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210S0561999-08-12012 August 1999
Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3
ML20210Q6161999-08-12012 August 1999
Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos
ML20217F2661999-08-12012 August 1999
Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator
ML20210R9231999-08-11011 August 1999
Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999
Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl
ML20210H4291999-07-29029 July 1999
Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs
ML20210F9451999-07-27027 July 1999
Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790
ML20210D3171999-07-23023 July 1999
Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr
05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999
Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached
ML20210D8701999-07-23023 July 1999
Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3
ML20210B1521999-07-15015 July 1999
Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations
ML20209G9771999-07-13013 July 1999
Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654
IR 05000382/19990081999-07-12012 July 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503
ML20209E5231999-07-0909 July 1999
Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583
ML20209D4051999-07-0707 July 1999
Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode
1999-09-09
[Table view]
Category:NRC TO UTILITY
MONTHYEARML20058E8621990-11-0101 November 1990
Forwards Understanding of Current Status of Unimplemented GSIs at Facility,Per 900626 Response to Generic Ltr 90-04. Timely Completion of Encl GSIs Urged
ML20058G1561990-10-31031 October 1990
Requests That Matl Listed in Encl 1, Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams, Be Furnished by 901207 for Retake of Operating Exams Scheduled for 910122
ML20058B3101990-10-23023 October 1990
Forwards Insp Rept 50-382/90-22 on 900905-1001 & Notice of Violation
IR 05000382/19900231990-10-17017 October 1990
Submits Revised Schedule for Electrical Distribution Sys Functional Insp 50-382/90-23.Insp Team Will Arrive at Plant Site on 910107
ML20058B2681990-10-17017 October 1990
Informs That Util Response to Generic Ltr 90-03, Relaxation of Staff Position in Generic Ltr 83-28,Item 2.2 Part 2, 'Vendor Interface for Safety-Related Components,' Acceptable
ML20058A6711990-10-16016 October 1990
Forwards Insp Rept 50-382/90-21 on 900910-14.No Violations or Deviations Noted
ML20058A4771990-10-16016 October 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-17
ML20062B6231990-10-12012 October 1990
Confirmation of Action Ltr CAL-90-06,confirming That Plant Will Not Enter Mode 2 Until NRC Confirms Actions Assuring That Adequate Safety Exists for Continued Power Operation
IR 05000382/19900151990-10-11011 October 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-15.NRC Unable to Clearly Determine Actions Intended to Address Overall Retest & Program Weaknesses
ML20059N7041990-10-10010 October 1990
Ack Receipt of Util 900717 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount
ML20059K8651990-09-14014 September 1990
Forwards Interfacing Sys LOCA Insp Rept 50-382/90-200 on 900730-0810.Deficiencies in Availability of Design Calculations,Check Valve Maint & Plant Equipment Labeling Noted
ML20059K3601990-09-14014 September 1990
Ack Receipt of Scenario for 1990 Emergency Preparedness Exercise
ML20059D5901990-08-28028 August 1990
Forwards Insp Rept 50-382/90-17 on 900625-29.No Violations or Deviations Noted.Exercise Weakness Re Performance of Emergency Responders Noted
ML20056B4841990-08-22022 August 1990
Forwards Errata to Amend 62 to License NPF-38,consisting of Revised Bases Page Re Time Intervals for Surveillance Requirements,Per 900717 Application & Generic Ltr 89-14
ML20056B2731990-08-16016 August 1990
Ack Receipt of 900720 & 0803 Ltrs Re Objectives & Guidelines for Annual Emergency Preparedness Exercise.Objectives Appear Reasonable.Exercise Scenario & Associated Matls Should Be Submitted at Least 60 Days Prior to Exercise for NRC Review
ML20058P3441990-08-15015 August 1990
Advises That Although Adequate Info Provided to Justify Continued Plant Operation Until Plant Completes Final Rept Per Schedule Delineated by NRC Bulletin 88-11,adequate Bases Not Provided for 40-yr Plant Life
ML20056A0301990-07-30030 July 1990
Forwards Insp Rept 50-382/90-11 on 900625-29.No Violations or Deviations Noted
IR 05000382/19900021990-07-27027 July 1990
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/90-02
ML20055G7951990-07-19019 July 1990
Forwards Insp Rept 50-382/90-14 on 900625-29 & Notice of Violation.Actions Taken Re Previously Identified Insp Findings Also Examined
ML20055E6501990-07-0909 July 1990
Discusses Generic Implications & Resolutions of Control Element Assembly (CEA) Failures at Maine Yankee.Waterford Unit 3 Does Not Have Old Style CEAs Installed in Reactor Core & Does Not Plan to Use Any in Future
ML20055C9751990-06-26026 June 1990
Forwards Page 6a for Insertion in Insp Rept 50-382/90-09
ML20055C7781990-06-15015 June 1990
Forwards Insp Rept 50-382/90-09 on 900501-31.No Violations or Deviations Noted.One Unresolved Item Identified.Licensee Test Acceptance Criteria Did Not Appear to Account for Effect of Flow on Valve Closing Time
ML20059M9171990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
ML20055C4121990-03-0202 March 1990
Ack Receipt of & Check for $50,000 in Payment for Civil Penalty Imposed by NRC 900202 Order.Corrective Actions Will Be Examined During Future Insp
ML20055C2991990-02-23023 February 1990
Advises That 890410 Changes to Emergency Plan,Acceptable
ML20248G1871989-10-0202 October 1989
Forwards Insp Rept 50-382/89-25 on 890828-0901.No Violations or Deviations Noted
ML20248C6531989-09-27027 September 1989
Forwards Insp Rept 50-382/89-23 on 890801-31.Violations Noted.Enforcement Conference Scheduled for 891011 in Region IV Ofc to Discuss Violation,Reason for Occurrence & Corrective Actions
ML20248A4091989-09-26026 September 1989
Requests That Jl Pellet Be Removed from Distribution for Controlled Documents Updates & Revs
ML20247Q4211989-09-22022 September 1989
Provides Results of Review of Amend to Rev 5 of Inservice Testing Program for Pumps & Valves.Amend to Rev 5 Acceptable for Implementation & That Testing Requirements Impractical for Item for Which Relief Being Granted
ML20247R5681989-09-21021 September 1989
Forwards Amend 4 to Indemnity Agreement B-92,reflecting Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, for Signature
ML20247J6851989-09-15015 September 1989
Forwards Insp Rept 50-382/89-16 on 890717-21 & Notice of Violation
ML20247D4781989-09-11011 September 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-05
ML20247F2211989-09-0808 September 1989
Forwards SER Accepting Util 881007,890203,0301 & 0717 Ltrs Re Compliance W/Atws Rule 10CFR50.62
ML20247H8501989-09-0808 September 1989
Ack Receipt of 890531 & 0821 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-07. NRC Disagrees W/Licensee Denial of Violation.Implementation of Corrective Actions Will Be Reviewed During Future Insp
ML20246P6081989-09-0606 September 1989
Forwards Summary of 890712 Meeting w/C-E Owners Group & Utils Re General Design Features of Diverse ESFAS to Be Installed,Per 10CFR50.62.Safety Evaluation on Plant Design Expected to Be Issued in Near Future
ML20246N3131989-08-31031 August 1989
Ack Receipt of Re Violations Noted in Insp Rept 50-382/89-08 & 890516 Notice of Violation.Requests Supplemental Response Re Examples 1-3 of Notice
ML20247A5841989-08-30030 August 1989
Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818.Agenda & List of Attendees Also Encl
ML20246M6491989-08-29029 August 1989
Forwards Amend 56 to License NPF-38 & Safety Evaluation. Amend Increases Frequency of Channel Calibrs from Quarterly to Monthly on Waste Gas Holdup Sys Explosive Gas Monitoring Sys
ML20245J0021989-08-14014 August 1989
Confirms 890808 Conversation W/Rp Barkhurst Re Util Participation in NRC Impact Survey Scheduled for 891010 & Submits Info Re Survey
ML20245L3311989-08-11011 August 1989
Forwards Insp Rept 50-382/89-22 on 890701-31 & Notice of Violation
IR 05000382/19890121989-08-11011 August 1989
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-12.Excluding Incident 1,Violation 382/8912-02 Should Stand as Cited. Response W/Corrective Actions Requested within 30 Days
ML20245J2451989-08-0909 August 1989
Advises That Requalification Exams Scheduled for Wk of 890911 Changed to Wk of 890905 to Accommodate New INPO Schedule Issued in May 1989
IR 05000382/19890051989-07-31031 July 1989
Discusses Insp Rept 50-382/89-05 on 890213-17 & Forwards Notice of Violation.No Addl Info Was Provided to Change NRC Position & Therefore Util in Violation of Requirements.Basis for NRC Determination of Violation Provided
IR 05000382/19890061989-07-28028 July 1989
Ack Receipt of 890706 Supplemental Response Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/89-06
1990-09-14
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217L0421999-10-21021 October 1999
Forwards Insp Rept 50-382/99-20 on 990815-0925 & Notice of Violation.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20217N2111999-10-19019 October 1999
Forwards Insp Rept 50-382/99-14 on 990913-17 & 1004-08.No Violations Noted.Licensed Operator Requalification Program, Effective,Utilized Systems Approach to Training & Showed Continued Improvements Over Previous Insp Findings
ML20217C6251999-10-0505 October 1999
Informs That NRC Reviewed Util Ltr & Encl Exercise Scenario Package for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Based on Review,Nrc Determined That Exercise Appropriate to Meet Objectives
ML20212J6921999-09-29029 September 1999
Forwards Insp Rept 50-382/99-18 on 990830-0902.One Noncited Violation Identified Re Failure to Follow Procedural Instructions to Ensure That Members on Fire Brigade Shift Were Qualified
ML20216G2441999-09-27027 September 1999
Forwards Insp Rept 50-382/99-19 on 990830-0903.No Violations Noted
IR 05000382/19993011999-09-21021 September 1999
Informs That NRC License Exam Previously Associated with NRC Insp Rept 50-382/99-301 Will Be Incorporated Into NRC Insp Rept 50-382/99-14
ML20212D8761999-09-16016 September 1999
Informs That on 990818,NRC Staff Completed Midcycle PPR of Waterford 3.During Assessment Period,Number of Personnel Errors Occurred,Which Demonstrated Lack of Attention to Detail by Plant Personnel.Historical Listing of Issues,Encl
ML20212C5881999-09-14014 September 1999
Forwards Insp Rept 50-382/99-15 on 990719-23 with Continuing in Ofc Insp Until 0819.No Violations Noted
ML20211Q4421999-09-0909 September 1999
Forwards Insp Rept 50-382/99-07 on 990601-11.Three Violations Being Treated as Noncited Violations
ML20211K9741999-09-0101 September 1999
Forwards Insp Rept 50-382/99-16 on 990704-0814.Two Severity Level IV Violations Identified & Being Treated as Noncited Violations,Consistent with App C of Enforcement Policy
ML20211G5751999-08-27027 August 1999
Forwards RAI Re IPEEE Submittal.Please Provide RAI within 60 Days of Receipt of Ltr,Per Util Response to GL 88-20,suppl 4
ML20211F4611999-08-24024 August 1999
Informs That NRC Reviewed Ltr & Encl Objectives for Waterford 3 Emergency Plan Exercise Scheduled for 991013.Exercise Objectives Appropriate to Meet Emergency Plan Requirements
ML20211G1731999-08-23023 August 1999
Informs That Info Submitted in ,B&W Rept 51-1234900-00,will Be Withheld from Public Disclosure,Per 10CFR2.790
ML20210T9791999-08-18018 August 1999
Discusses Which Responded to Reconsideration of Violation Denial (EA 98-022) Enforcement Action Detailed in .Concludes That Violation Occurred as Stated
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210R9231999-08-11011 August 1999
Forwards Insp Rept 50-382/99-10 on 990719-23.Violations Noted.Nrc Has Determined That One Severity Level IV Violation of NRC Requirements Occurred
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210D8701999-07-23023 July 1999
Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 Through ISI-020 for Entergy Operations,Inc,Unit 3
ML20210B1521999-07-15015 July 1999
Forwards Insp Rept 50-382/99-13 on 990523-0703.Three Violations Being Treated as Noncited Violations
IR 05000382/19990081999-07-12012 July 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-08 Issued on 990503
ML20209E5231999-07-0909 July 1999
Informs That as Result of NRC Review of Util Responses to GL-92-01,rev 1 & Suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2.This Closes Staff Efforts Re TAC MA0583
ML20196E6931999-06-22022 June 1999
Forwards Corrected Ltr Re Changes to Rev 19 to Emergency Plan.Original Ltr Had Error in Subject Line
ML20196E0831999-06-21021 June 1999
Forwards Insp Rept 50-382/99-12 on 990524-27.No Violations Noted.Purpose of Insp Was to Conduct Assessment of Emergency Preparedness Program
ML20196D9941999-06-18018 June 1999
Forwards Insp Rept 50-382/99-11 on 990524-28.No Violations Noted
ML20195J8091999-06-17017 June 1999
Forwards Safety Evaulation Re First 10-yr Interval Inservice Insp Relief Request for Plant,Unit 3
ML20196C8711999-06-15015 June 1999
Discusses Insp Rept 50-382/99-08 & Forwards Notice of Violation Re Unescorted Access Which Was Mistakenly Granted to Individual Whose Background Investigation Indicated That He Had Failed Prior Drug Screening with Another Employer
ML20196F3721999-06-0909 June 1999
Corrected Ltr Forwarding Rev 19 to Emergency Plan
ML20195G3711999-06-0909 June 1999
Ack Receipt of Ltr Dtd 981223,which Transmitted Waterford 3 Steam Electric Station Emergency Plan,Rev 24,under Provisions of 10CFR50,App E,Section V.No Violations of 10CFR50.54(q) Identified During Review
ML20207E8541999-06-0303 June 1999
Forwards SE Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressurizer Safety Valves at Plant,Unit 3
ML20207G3441999-06-0303 June 1999
Forwards Insp Rept 50-382/99-09 on 990411-0522 & Notice of Violation.One Violation Identified & Being Treated as Noncited Violation C
ML20207D3771999-05-27027 May 1999
Ack Receipt of 990401 & 0504 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-382/99-01 on 990303
ML20207A5121999-05-24024 May 1999
Refers to Which Responded to NOV & Proposed Imposition of Civil Penalty Sent by .Violations A,B & E Withdrawn & Violations C & D Changed to Severity Level IV
ML20206U7851999-05-18018 May 1999
Forwards Insp Rept 50-382/99-06 on 990405-09.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations
ML20206N6961999-05-11011 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created
ML20206S4411999-05-10010 May 1999
Forwards Insp Rept 50-382/99-05 on 990228-0410.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20206H3841999-05-0707 May 1999
Informs That on 990407,NRC Administered Generic Fundamental Exam Section of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However Copy of Master Exam,With Answer Key,Encl for Info.Without Encl
ML20206K0951999-05-0606 May 1999
Discusses Insp Rept 50-382/99-08 Issued 990503 Without Cover Ltr Documenting EA Number & Subject Line Indicated NOV Which Was Incorrect.Corrected Cover Ltr Encl
ML20206F4701999-05-0303 May 1999
Forwards Insp Rept 50-382/99-08 on 990405-07.One Apparent Violation Re Failure to Review & Consider Derogatory Access Authorization Background Info as Required by PSP Identified & Being Considered for Escalated Enforcement Action
ML20206K1211999-05-0303 May 1999
Corrected Cover Ltr Forwarding Insp Rept 50-382/99-08 on 990405-07.One Violations Noted & Being Considered for Escalated EA
ML20205N7251999-04-13013 April 1999
Forwards Summary of 990408 Meeting with EOI in Jackson, Mississippi Re EOI Annual Performance Assessment of Facilities & Other Issues of Mutual Interest.List of Meeting Attendees & Licensee Presentation Slides Encl
ML20205M0561999-04-0909 April 1999
Forwards Insp Rept 50-382/99-04 on 990301-19.One Violation of NRC Requirements Occurred & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy
ML20205J8781999-04-0505 April 1999
Forwards Insp Rept 50-382/99-02 on 990117-0227.No Violations Noted.Inspectors Determined That Six Violations Occurred & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy
ML20205J0901999-04-0202 April 1999
Informs That Info Submitted by & 970313 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b) (5)
ML20205A4681999-03-26026 March 1999
Forwards Insp Rept 50-382/99-03 on 990308-12.Two Violations of Radiation Protection Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20205A6141999-03-25025 March 1999
Forwards SE Accepting Request to Use Mechanical Nozzle Seal Assemblies (Mnsas) as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Application at Plant,Unit 3
ML20205F3311999-03-19019 March 1999
Advises of Planned Insp Effort Resulting from Plant,Unit 3 PPR Review,Which Was Completed on 990211.Performance at Plant,Unit 3 Was Acceptable
ML20204E4941999-03-17017 March 1999
Discusses TSs Bases Change Re 3/4.4.1,3/4.6.1.7,3/4.6.3, 3/4.7.12 & 3/4.8.4.Forwards Affected Bases Pp B 3/4 4-1, B 3/4 6-3,B 3/4 6-4,B 3/4 7-7 & B 3/4 8-3
ML20207F1251999-03-0303 March 1999
Forwards Insp Rept 50-382/99-01 on 990125-29 & 0208-12 & Notice of Violations
ML20203H8501999-02-17017 February 1999
Forwards SE Accepting Licensee 970701 Submittal of Second Ten Year ISI Program & Associated Relief Request for Plant, Unit 3.Nine Relief Requests Had Been Authorized Previously & Proposed Alternatives Remain Authorized
ML20203D7211999-02-11011 February 1999
Forwards Request for Addl Info Re Licensee 970317 & 990111 Responses to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Response Should Be Provided within 60 Days
1999-09-09
[Table view] |
Text
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.*'s In Reply Refer To:
Docket: 50-382/86-34
$1W Louisiana Power & Light Company ATTN: J. G. Dewease, Senior Vice President Nuclear Operations 317 Baronne Street New Orleans, Louisiana 70160 Gentlemen:
Thank you for your letter of June 18, 1987, in response to our letter and Notice of Violation dated May 19, 198 We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely,
~
- :ct Signed by; WLU J. E. Gagliardo, Chief Reactor Projects Branch cc:
Louisiana Power & Light Company ATTN: G. E. Wuller, Onsite Licensing Coordinator P. O. Box B Killona, Louisiana 70066 Louisiana Power & Light Company ATTN: N. S. Carns, Plant Manager P. O. Box B Killona, Louisiana 70066 Middle South Services ATTN: Mr. R. T. Lally P. O. Box 61000 New Orleans, Louisiana 70161 f'
RIV:RSB/0S Tapia:gb 05 @
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TFWesterman RPB JEGagliardo 6/Q/87 '5 / 4 /87 g/f/87 9/1/87 pf/87 870BO70120 870004 PDR G
ADOCK 05000382 PDR
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Louisiana Power & Light Company 2 Louisiana Power & Light Company ATTN: K. W. Cook, Nuclear Safety and Regulatory Affairs Manager 317 Baronne Street P. 0. Box 60340 New Orleans, Louisiana 70160 Louisiana Radiation Control Program Director bec to DMB (IE01)
bec distrib. by RIV:
- Section Chief (RPB/A) DRSP RPSB *RSB
- MIS System * Project Inspector, RPB
- RIV File *J. Wilson, NRR Project Manager J. Tapia SectionChief(RSB/05)
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LOUISI& AN POWER A LIGHT / 317NEW BARONNESTREET * P. O. BOX 60340 ORLEANS, LOUISIANA 70160 + (504) 595-3100
$@i?O sYsVIO June 18, 1987 W3P87-1700 A4.05 QA U.S. Nuclear Regulatory Commission I IN@[5IlV//:
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ATTN: Document Control Desk 'I f
Washington, D.C. 20555 j M l 9 lg8'[
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w Subject: Waterford 3 SES l Docket No. 50-382 -
License No. NPF-38 NRC Inspection Report 86-34 Attached is the Louisiana Power and Light Company (LP&L) response to l Violation No. 8634-01 identified in Inspection Report No. 86-3 If you have any questions on the response, please contact G.E. Wuller, Operational Licensing, at (504) 464-349 Very tr y yours, jk Ye .v
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K.W. [ook Nuclear Safety and Regulatory Affairs Manager KWC:PTM:pmb Attachment cc: R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office E.L. Blake W.M. Stevenson 54 ~
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( "AN EQUAL OPPORTUNITY EMPLOYER" fc41 1%i
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- , o Attachnsnt to W3P87-1700 Sheet 1 of 2 LP&L Response to Violation No. 8634-01 VIOLATION NO. 8634-01 Failure to Quantify Containment Isolation Valve Leakage The requirements of Appendix J to 10CFR Part 50.54(o), are invoked as a condition of the license for all water cooled power reactors. Appendix J requires that a continuous running tum of local leak rates for penetrations and isolation valves subjected to this testing not exceed 0.6 times the maximum allowable leakage rate at the calculated peak containment internal pressure related to the design basis loss of coolant acciden Contrary to the above, it was found during the week of December 8-11, 1986 that the local leak rates for six valves required to be tested had recorded as-found leak results of "off-scale" with no recorded value, so that the continuous running sum of local leak rates was not known and the required comparison with the Appendix J criterion could not be made for the as-found conditio This is a Severity Level IV violatio RESPONSE (1) Reason for the Violation The requirements of Appendix J Section III.C.3 to 10CFR Part 50 as invoked through Part 50.54(o) states in part: "The combined leakage rate for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La." At the time the local leak rate testing was being performed the plant was in Mode As the result of local leak rate testing, six valves had as-found leak rates which exceeded the capability of the test equipmen The data as recorded was identified as "off scale" with no numerical value identified. During this inspection the NRC inspector noted that because of the recorded values of "off scale" he was unable to ascertain if the criterion of 0.60 La for leakage was satisfie (2) Corrective Action That Has Been Taken Prior to performing maintenance on the six valves the local leak rate test configuration was modified to provide a greater flow measuring capability. Of the six valves identified as having leak rates of "off scale", numerical values were identified for 5 of these valves. The sixth valve, a 24 inch contc1nment vacuum check valve (CVR-102) could not be pressurized with the modified test unit, thus r.o leak rate could be establishe Correctiva action was initiated by maintenance on all six valves and the appropriate retests were conducted. Acceptable leak rates were .
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identified for these valves prior to returning to Mode 4. In accordance with the Appendix J criterion the required comparison for
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- '# Attachment to W3P87-1700 Sheet 2 'f 2 the as-found condition could not be made for CVR-10 For the purpose of this test it was assumed that the leakage for CVR-102 wculd result in exceeding the 0.60 La limi As per Appendix J Section V. requirements this valve will be reported in a separate accompanying summary report to the " Reactor Containment Building Integrated Leak Rate Test" repor The ability to indicate and quantify leakage ratea has been increased to account for valves with larger leak rate A continuous running sum total leak rate has been established to be able to, at any time, identify present leakage as compared to the 0.60 La limi It is conceivable in the future that a gross leskage may exceed the capability of our test uni In this event, alternative test methods or evaluations will be conducted to determine whether the 0.60 La criteria for Type C testing is met and a summary report will be prepared in accordance with Appendix J Section V. (3) Corrective Action To Be Taken Surveillance Procedure (PE-5-002) " Local Leak Rate Test (LLRT)" will be modified to maintain a continuous running sum of leak rates that fall within the 0.60 La criteria. Failed valves will be reworked and retested to ensure the total leakage is less than 0.60 La prior to entering a mode where the requirement exist (4) Date When Full Compliance Will Be Achieved Changes to the surveillance Procedure " Local Leak Rate Test (LLRT) are expected to be complete by July 15, 198 .
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