|
|
(One intermediate revision by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML20155G267 | | | number = ML20155G267 |
| | issue date = 10/04/1988 | | | issue date = 10/04/1988 |
| | title = Ack Receipt of 880912 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/88-15 & 50-362/88-16 | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/88-15 & 50-362/88-16 |
| | author name = Zimmerman R | | | author name = Zimmerman R |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
Line 11: |
Line 11: |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8810140172 | | | document report number = NUDOCS 8810140172 |
| | | title reference date = 09-12-1988 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 1 | | | page count = 1 |
Line 18: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:. |
| | . l |
| | . o .. . |
| | 007 - 4 1988 Docket Nos. 50-361, 50-362 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attn: Mr. Kenneth P. Baskin, Vice President Nuclear Engineering, Safety, and Licensing Department Gentlemen: |
| | Thank you for your letter of September 12, 1988, in response to our Notice of Violation and Inspection Report No. 50-361/88-15 and 50-362/88-16, dated August 12, 1988, informing us of the steps you have taken to correct the items which sie brought to your attention. Your corrective actions will be verified during a future inspectio Your cooperation with us is appreciate |
| | |
| | Sincerely, |
| | |
| | R. erman, Chie Reactor Projects Branch bec w/ copy of letter dated 9/12/88: , |
| | Resident Inspector Project Inspector G. Cook A. Johnson B. Faulkenberry J. Martin Docket File LFMB State of California l l |
| | bec w/o copy of letter dated 9/12/88: |
| | M. Smith u rg JTa M A |
| | # sin RZ Nan 10/ /88 10/ t//88 10/([/88 10/f/88 1f/88 ern ;mm . ;mm V V v e r wro v v j TO POR ' |
| | ES / No .1 i\ \ |
| | $0bb? $$$@@jg / |
| | PDC |
| | |
| | . .. .t.. |
| | , , ee * |
| | - . |
| | ' |
| | *s Southem Califomla Edison Co any P. O. BO X 800 g , |
| | 2244 WALNUT GROVE AVENUE ROS EM EAD. CALIFORNIA 91770 v'C E P t et sie 308 01 September 12, 1988 |
| | ! |
| | . |
| | U. S. Nuclear Regulatory Commission' |
| | Attention: Document Control Desk Hashington, D.C.' 20555 - |
| | Gentlemen: |
| | Subject: Docket Numbers 50-361 and 50-362 |
| | ' |
| | Reply to a Notice of Violation and Notice of Deviation San Onofre Nuclear Generating Station Units 2 and 3 Reference: Letter, Hr. J. B. Hartin (NRC) to Mr. Kenneth Baskin (SCE), dated August 12, 1988-l l |
| | The above referenced letter forwarded NRC Inspection Report Nos. 50-361/88-15 l and 50-362/88-16, a Notice of Violatio.1 and a Notice of Deviation resulting l from the routine inspections conducted by Hessrs. F. R. Huey, J. E. Tatum, A. L. Hon, and A. D. Johnson during the period May 22 through July 2,198 In accordance with 10 CFR 2.201, Enclosures A and B to this letter provide the Southern California Edison (SCE) reply to the subject Notice of Violation and |
| | , |
| | Notice of Deviation, respectivel j |
| | ! |
| | If you require any additional information. please so advis Very truly yours, S4 h J Enclosures: as stated cc: J. 8. Hartin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3 |
| | .f2rtru g, s 01.nnm.- f lf < |
| | ' |
| | - - . |
| | |
| | * .= ., .. |
| | . . .. |
| | t |
| | ' |
| | ENCLOSURE A REPLY TO THE NOTICE OF VIOLATION |
| | . |
| | Appendix A to Mr. J. B. Hartin's letter, dated August 12, 1988, states in part: |
| | "10 CFR Part 50, Appendix B, Criterion V provides, in part, that: |
| | ' Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.' |
| | "Chapter SC (Revision 10) of the. licensee's TQAM, paragraph 8 . states only measuring and test equipment evidencing a current calibration status shall be used for safety related activitie "Paragraph 6.13.2.4 of Haintenance Procedure S0123-I-1.7 (TCN 2-2) states that the journeyman shall draw and inspect all measuring and test equipment to be used for the activity to ensure that the calibration date will remain valid for the duration of the activity, and shall record the instrumentation used on the maintenance order (HO). |
| | |
| | "Contrary to the above requirements: |
| | " On June 17, 1988, a strip chart recorder (H&TE #I2,9097) with a calibration due date of June 16, 1988, and a D. C. amplifier (H&TE #I2-8696) with a calibration due date of June 14, 1988, were being used to gather data to evaluate operability of the post-LOCA hydrogen monitoring system (Train B). |
| | |
| | " The measuring and test equipment being used to evaluate the operability of the post-LOCA hydrogen monitoring system (Train B) was not recorded on the applicable H0, No. 8806060 "This is a Severity Level IV violation (Supplement I)." |
| | |
| | RESPONSE Reasons for the violation, if admitted SCE admits that contrary to procedure $0123-I-1.7, "Maintenance Order Preparation, Use And Scheduling " (A) measuring and test equipment (H&TE) was used which had expired stickerst and (8) the H&TE was not recorded on the maintenance order. SCE's investigation has established that there is no safety significance to this even The facts and circumstances surrounding each of these issues are as |
| | , follows: |
| | . |
| | ,_ .---,--.n.-- - - - - - - - - - . - , - . |
| | ,- , .- - - - , , _ . - - - , |
| | |
| | a .. . .. |
| | . . .. . |
| | o |
| | , -2- |
| | . Use of H&TE with Expired Calibration Stickers SCE's investigation determined that the strip chart recorder - |
| | and the DC amplifier were attached to the Train 8 post-LOCA hydrogen monitoring system to collect investigative information on June 8, 1988. When the I&C technician attached the strip chart recorder and the DC amplifier to the hydrogen monitoring system, he verified that their calibration stickers had not expired. He was aware that on or before the calibration due dates, they should be returned for calibration in accordance with the Station's H&TE recall progra However, due to the in'vestigative nature of the activity, it was not known and therefore not specified in the H0 as to how |
| | ,long such information gathering would las The H&TE was left connected to the Hydrogen Monitoring System beyond the calibration due dates. The investigative information obtained on the Train 8 post-LOCA hydrogen monitor was not used to evaluate operability in accordance with Technical Specification surveillance requirements. Instead, the information gathered with this equipment was used by the cognizant engineer to develop potential corrective action Subsequent to these actions, Technical Specification operability surveillances were performed using M&TE within the required calibration due date In summary, personnel error, exacerbated by the open-ended nature of the investigative activity, resulted in the use of the H&TE two days beyond its calibration due dat Notwithstanding this, the information gathered by the equipment was not used as the basis for determining operabilit i H&TE Not Recorded on H0 ! |
| | Procedure S0123-I-1.7 is the general procedure governing the maintenance order control process. This procedure requires that the H&TE used be documented on the H0. In addition, procedures 50123-II-1.0, "Calibration And Control of Measuring And Test Equipment," and S0123-II-1.2, "Preparation and l |
| | Responsibility of the M&TE Traveler," require that when H&TE is issued, a corresponding H&TE traveler is also issued to record i i |
| | the activities (maintenance order, construction work order, ! |
| | etc..) for which the M&TE is used. These two procedures provided guidelines under which an H&TE could be considered |
| | "Not Used" and be recorded as such on the H&TE traveler. The |
| | , |
| | technician erroneously believed that these guidelines provided the applicable guidance for recording "None" under the "Test l Equipment /Special Tools Used" section of H0 8806060 i |
| | - _ . . _ - . - - - - - , - - - |
| | |
| | i .. . .. |
| | . . . ~ |
| | ' |
| | -3- |
| | . |
| | In summary, contrary to procedure S0123-I-1.7, the strip chart recorder and the DC amplifier used were not recorded on H0 88060605. This was caused by procedural ambiguity within and between procedures governing the work activitie . Corrective steps that have been taken and the results achieved On June 17, 1988, the strip chart recorder and the DC amplifier were removed from the Train 8 post-LOCA hydrogen monitoring syste This event was discussed with all appropriate Units 2/3 I&C technician To be consistent with proced'ure S0123-I-1.7, which requires that all H&TE used be recorded in the H0, procedur6s 50123-II-1.0 and S0123-II-1,2 have been revised to require that all activities for which the H&TE is used, be recorded in the H&TE travele . |
| | Corrective actions that will be taken to avoid further violations Regardless of the nature of the activities involved, the use of H&TE with a current calibration sticker is a matter of station policy and is required by station procedures. Clearly, the use of the H&TE with expired calibration stickers was contrary to the station policy and procedures. It is SCE's position to require the use of H&TE with a current calibration sticker. Consequently, a reading assignment, describing this event and emphasizing the need to verify that no H&TE will be used beyond its calibration due date, will be distributed to appropriate maintenance personne Future investigative maintenance activities of indeterminate duration, which involve the use of M&TE, will include administrative controls to enhance the consideration given by technicians to the calibration due dates vis-a-vis the expected completion of the investigative effor These corrective actions are expected to be completed by-November 15, 198 . Date when Tull compliance will be achieved Full compliance was achieved on June 17, 1988, when the H&TE with the expired calibration stickers was remove F |
| | . |
| | - - - _ . - - - . - - - - - .. .. - - - . - . |
| | |
| | i , . |
| | , |
| | . . - |
| | f ENCLOSURE B REPLY TO THE NOTICE OF DEVIATION Appendix B to Mr. J. B. Hartin's letter, dated August 12, 1988, states in part: |
| | "Paragraph 9.1.2.2 of the Updated Final Safety Analysis Report (Revision 4) for San Onofre Nuclear Generating Station Units 2 and 3 states: 'All connections to the spent fuel storage pool are made as to preclude the possibility of siphon draining of the pool.' |
| | "Contrary to the above, the fuel pool purification suction piping (015-4"-J-LLO) was found on June 22, 1988, to extend to the bottom of the spent fuel storage pool, and system features did not preclude the possibility of siphon draining of the pool." |
| | |
| | RESPONSE Reasons for the deviation, if admitted SCE admits that the June 22, 1988 system alignment of the spent fuel storage pool draining of thepiping pool.did not preclude the possibility of siphon The design of the spent fuel storage pool was completed in 197 In |
| | ' |
| | preparing the design to preclude the possibility of siphon draining of the pool, SCE utilized Section 9.1.1 of the NRC Standard Review l Plan which permits either the use of siphon breakers / check valves or other devices such as locked valves coupled with administrative controls preclude (procedures governing a siphon even < the use of the locked valves), to i |
| | In the case of the spent fuel storage pool purification line, a ' |
| | combination of locked closed valves and administrative controls were I intended to prevent inadvertent siphoning (notwithstanding that under certain circumstances the spent fuel pool skimmers may currently function as a siphon breaker). Valves HUO76 HU100, and HU101 were designated as locked closed valves. The Piping3 and Instrumentation Drawings (P& ids) were subsequently issued showing these as locked closed valve No basis was provided in the design documents which explained the |
| | , |
| | ' necessity for locking these valves closed. Consequently, when a revision to the Operations procedure S023-3-2.8.1, "Refueling Cavity Draining Operation", was prepared, the design intent of these valves was not fully understood, s |
| | . |
| | |
| | s .;>* . |
| | .% ~ |
| | ., . |
| | r-2-In addition, the Final Safety Analysis Report (FSAR), Section 9.1.2.2, description of the spent fuel storage pool and cooling systems cited above does not provide a complete description of the |
| | . |
| | design, including the use of administrative control . Corrective steps which have been taken and the results achieved Updated design information regarding administrative controls for the spent fuel storage pool piping and valves has been provided to appropriate personne Procedures regarding the operation of the spent fuel storage pool piping and valve alignments.have been revised to include appropriate ' |
| | precautions and controls to prevent potential future siphon alignment . Corrective steps which will be taken to avoid further deviations A design modification is being evaluated to deter'mine the feasibility and cost of a change to the system design to physically preclude the establishment of a sipho FSAR Section 9.1.2.2, "Spent Fuel Pool and Cooling Systems" will be revised at the next annual revision to describe the current design i and the use of administrative control Licensee Event Report (LER) number 88-017 (Docket No. 50-361), |
| | reported the siphoning event of Junt 22, 1988. As discussed in the , |
| | LER, a revision to the LER is being prepared which will include the above corrective action .- |
| | 4. The date when corrective action will be completed The revisions to applicable Operating procedures were completed on September 7, 198 F |
| | |
| | ! |
| | . |
| | l |
| | . |
| | ,--- |
| | . - - - - - -- - - - - - - - . --. , - ~ - . , , , - - , .,. , , , ---, ,. - - , - - , |
| }} | | }} |
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P7111999-10-26026 October 1999 Informs That Licensee 990330 Response to GL 97-06 Provides Reasonable Assurance That Condition of Licensee Steam Generator Internals Is in Compliance with Current Licensing Bases for Plant ML20217K3571999-10-21021 October 1999 Discusses Use of SONGS as Generic Safety Issue 191 Ref Plant.Future Requests for Info & Addl Coordination Activities Be Handled Through D Evans of Organization.With Diskette ML20217K8541999-10-21021 October 1999 Forwards Revised Pages to ERDS Data Point Library,Per Requirements of 10CFR50,App E,Section VI.3.a.Described Unit 2 & 3 Changes for 2/3R7813 Were Completed on 990924 ML20217L9491999-10-21021 October 1999 Forwards SONGS Emergency Response Telephone Directory, for Oct-Dec 1999 ML20217J8631999-10-15015 October 1999 Forwards Insp Repts 50-361/99-12 & 50-362/99-12 on 990808- 0918.One Violation Identified Involving Inoperability of Emergency Diesel Generator in Excess of Allowed Outage Time ML20217E3221999-10-13013 October 1999 Forwards MORs for Sept 1999 for Songs,Units 2 & 3.No Challenges Were Noted to Psvs for Either Units 2 or 3 ML20217E7671999-10-12012 October 1999 Forwards Rev 62 to NRC Approved Aug 1983, Physical Security Plan,Songs,Units 1,2 & 3, IAW 10CFR50.54(p).Changes,as Described in Encls 1 & 2,do Not Reduce Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20217B5981999-10-0606 October 1999 Informs That Staff Concluded That All Requested Info for GL 98-01, Year 2000 Readiness in Us Nuclear Power Plants, Provided for San Onofre Nuclear Generating Station,Units 2 & 3 ML20216H8741999-09-29029 September 1999 Provides Requested Written Response to GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal. Lab Testing of Charcoal Adsorber Samples for Creacus & Pacu Satisfies Listed Requirements ML20216H8541999-09-29029 September 1999 Submits Encl Request for Relief from ASME Code,Section III Requirements in 10CFR50.55(a)(3) to Use Mechanical Nozzle Seal Assembly as Alternate ASME Code Replacement at SONGS, Units 2 & 3 for Period of Operation Beginning with Cycle 11 ML20216J2631999-09-28028 September 1999 Forwards Copy of Final Accident Sequence Precursor (ASP) Analysis of Operational Event at Songs,Unit 2,reported in LER 361/98-003 ML20212H4461999-09-28028 September 1999 Forwards Suppl Info,As Discussed with NRC During 990812 Telcon,To Support Risk Informed Inservice Testing & GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20212G5611999-09-24024 September 1999 Informs NRC That SCE Remains Committed to Performing Eddy Current Examinations of 100% of Reactor Vessel Head Penetrations at Songs,Unit 3.Exams Will Not Be Performed During Cycle 11 RFO 05000361/LER-1999-005, Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments1999-09-23023 September 1999 Forwards 30-day follow-up LER 99-005-00,describing Loss of Physical Train Separation in Control Room.Any Actions Listed Intended to Ensure Continued Compliance with Existing Commitments ML20212D9921999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of San Onofre.Nrc Plan to Conduct Core Insps & One Safety Issues Evaluation of MOVs at Facility Over Next 7 Months. Details of Insp Plan Through March 2000 Encl ML20212A4061999-09-14014 September 1999 Forwards Revised Pages to ERDS Data Point Library.Described Unit 2 Changes for 2R7817 & 2R7828 Were Completed on 990818 & Unit 3 Change for 3R7828 Was Completed on 990903 ML20216E6031999-09-10010 September 1999 Provides Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams, Dtd 990820.Schedule Shown on Attachment 1, Operator Licensing Exam Data, Provides Util Best Estimate Through Cy 2003 ML20217B9011999-09-10010 September 1999 Responds to Which Addressed Concerns Re Y2K Issue & Stockpiling of Potassium Iodide (Ki) Tablets by Informing That San Onofre Nuclear Station Already Completed All Work Required to Be Ready for Y2K Transition ML20211K4191999-09-0303 September 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20211N0261999-09-0303 September 1999 Forwards Exemption from Certain Requirements of 10CFR50.44 & 10CFR50,app A,General Design Criterion 41 in Response to Util Request of 980910,as Supplemented 990719 & SER 05000206/LER-1999-001, Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 31999-08-31031 August 1999 Forwards LER 99-001-00 for Occurrence Re Unattended Security Weapon Inside Protected Area.Single Rept for Unit 1 Is Being Submitted,Iaw NUREG-1022,Rev 1,since Condition Involves Shared Sys & Is Applicable to Units 1,2 & 3 ML20211H3321999-08-30030 August 1999 Discusses 1999 Emergency Preparedness Exercise Extent of Play & Objectives.Based on Review,Nrc Has Determined That Exercise Extent of Play & Objectives Are Appropriate to Meet Emergency Plan Requirements ML20211J7151999-08-27027 August 1999 Forwards Insp Repts 50-361/99-09 & 50-362/99-09 on 990627- 0807.Two Violations Being Treated as non-cited Violations ML20211H8561999-08-23023 August 1999 Forwards SE Accepting Licensee 970625 Requests for Relief RR-E-2-03 - RR-E-2-04 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211J5821999-08-23023 August 1999 Corrected Copy of ,Changing Application Date from 970625 to 990625.Ltr Forwarded SE Accepting Licensee 990625 Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section XI as Listed ML20210V4271999-08-16016 August 1999 Forwards Proprietary Certified Renewal Applications for SROs a Harkness,R Grabo & T Vogt & RO D Carter,Submitted on Facsimile Form NRC-398 & Certified NRC Form 396.Encls Withheld ML20210R6681999-08-13013 August 1999 Forwards Response to NRC RAI Re SCE License Amend Applications 173 & 159 for Songs,Units 2 & 3,proposed Change Number 485,which Requests Addition of SR to TS 3.3.9, CR Isolation Signal 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 ML20210Q6451999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for SONGS, Units 2 & 3,per TS 5.7.1.4.There Were No Challenges to Pressurizer Safety Valves for Either Units ML20210P5711999-08-11011 August 1999 Forwards Amend Application Number 189 for License NPF-10 & Amend Application Number 174 to License NPF-15,replacing Analytical Limits Currently Specified as Acceptance Criteria with Allowable Values,Per Encl Calculation E4C-098 ML20210P4681999-08-11011 August 1999 Forwards COLR for Cycle 10 for Songs,Units 2 & 3,IAW TS Section 5.7.1.5.d, Colr. Changes to COLR Parameters Have Been Conducted IAW Approved COLR Methodologies & All Applicable Limits of Safety Analysis Were Met ML20210P6221999-08-10010 August 1999 Forwards Replacement Pages for Attachments E & F of Amend Application Numbers 168 & 154 for Songs,Units 2 & 3.Pages Are Provided to Correct Errors to Pagination & Headings in 970618 Submittal ML20210N9721999-08-10010 August 1999 Responds to Appeal of FOIA Request for Documents Re Osre Issue.No Osre Visit Scheduled for Sept 1996 at Plant,Per 990722 Telcon.V Dricks,In Ofc of Public Affairs Should Be Contacted Re Osre Issue ML20210N0901999-08-0909 August 1999 Informs That 990312 Application Requested Amends to Licenses DPR-13,NPF-10 & NPF-15,respectively,being Treated as Withdrawn.Proposed Change Would Have Modified Facility TSs Pertaining to SONGS Physical Security Plan ML20210N5051999-08-0909 August 1999 Forwards Cycle 10 Update to TS Bases,Which Have Been Revised Between 980101-990630,per 10CFR50.71(e) 05000361/LER-1999-004, Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl1999-08-0606 August 1999 Forwards LER 99-004-00 Re Automatic Tgis Actuation.Event Affected Units 2 & 3 Equally Because Tgis Is Shared Sys. Single Rept Is Being Provided for Unit 2 IAW NUREG-1022, Rev 1.No New Commitments Are Contained in Encl ML20210L2311999-08-0505 August 1999 Forwards ISI Summary Rept,Including Owners Repts of Repairs & Replacements,For Songs,Unit 3.Rept Covers 970916 Through 990509,date Unit 3 Returned to Service Following Cycle 10 Refueling Outage 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 ML20216D9671999-07-29029 July 1999 Provides Response to RAI to Support Proposed TS Change 460 Re Containment Isolation Valve Completion Time for SONGS, Units 2 & 3.Rev 3 to Abnormal Operating Instruction SO23-13-14, Reactor Coolant Leak, Encl ML20210C1821999-07-22022 July 1999 Forwards Rept Providing Results of Insp of Eggcrate Tube Supports Done on Secondary Side of Sgs,Using Remote Controlled Visual Equipment ML20210B2451999-07-21021 July 1999 Forwards Response to NRC 990615 RAI Re GL 95-07, Pressure Locking & Thermal Bldg of SR Power-Operated Gate Valves, for Songs,Units 2 & 3 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies ML20209J5241999-07-19019 July 1999 Provides Clarification of Util Intentions Re Disposition of Systems for Which Exemption & TS Changes Were Requested in Licensee .Deferment of Action Re Hydrogen Monitors,Encl ML20210N2881999-07-19019 July 1999 Forwards Rev 61 to Physical Security Plan,Rev 21 to Safeguards Contingency Plan & Rev 20 to Security Force Training & Qualification Plan,Per 10CFR50.54(p),for Plant. Screening Criteria Forms Encl.Plans Withheld ML20210A2911999-07-19019 July 1999 Submits Withdrawal Request Submitted by Ltr Dtd 990312, Requesting NRC Approval of Revs to Physical Security Plan & Safeguards Contingency Plan Tactical Response Plan ML20209G3421999-07-15015 July 1999 Forwards Table of 16 Affected Tube Locations in SG E089, Discovered During Cycle 10 Outage Insp,Which Were Probably Not Examined by Bobbin During Cycle Outage Insp ML20209D8051999-07-12012 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20209F5681999-07-0909 July 1999 Forwards Insp Repts 50-361/99-08 & 50-362/99-08 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20209C1571999-07-0202 July 1999 Forwards Response to NRC RAI Re SCE Submittal Dtd 980710,re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20196K6721999-07-0202 July 1999 Discusses 990628 Meeting Conducted in Region IV Office Re Status of San Onofre Nuclear Generating Station Emergency Preparedness Program.List of Attendees & Licensee Presentation Encl 1999-09-03
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F9441990-11-0909 November 1990 Forwards Insp Repts 50-206/90-35,50-361/90-35 & 50-362/90-35 on 901009-12.No Violations Noted ML20058G5571990-11-0505 November 1990 Provides Corrections to Insp Repts 50-206/90-33,50-361/90-33 & 50-362/90-33,per ML20058B9291990-10-22022 October 1990 Forwards Ref Matl Requirements for Requalification Program Evaluation at Units 2 & 3 During Wk of 910122-0201 ML20059N9351990-10-0303 October 1990 Forwards Insp Repts 50-206/90-33,50-361/90-33 & 50-362/90-33 on 900904-07.No Violations Noted ML20059L1611990-09-18018 September 1990 Provides Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010.W/o Encls ML20059G9751990-08-21021 August 1990 Forwards Insp Repts 50-206/90-31,50-361/90-31 & 50-362/90-31 on 900731-0803.No Violations Noted ML20059A4621990-08-16016 August 1990 Advises That 900717 Response to NRC Bulletin 90-001, Loss of Fill Oil in Transmitters Mfg by Rosemount, Served as Basis for Closing Issue on Unit 1.Results of Evaluation of Units 2 & 3 Will Be Subj of Future Ltr ML20058P2911990-08-0101 August 1990 Forwards Initial Licensing Exam Rept 50-361/OL-90-02 on 900618-29 for Units 2 & 3.Fifteen of 19 Candidates Passed Exam IR 05000206/19900101990-07-26026 July 1990 Ack Receipt of Advising of Steps Taken to Correct Violations Noted in Insp Repts 50-206/90-10,50-361/90-10 & 50-362/90-10.Identification of New Info Provided Addl Useful Info on Recent Check Valve Activities at Facility ML20055H7451990-07-24024 July 1990 Requests Util Provide Listed Ref Matls for Reactor & Senior Reactor Operator Licensing Exams on 901023-25 ML20058L8981990-07-23023 July 1990 Forwards Insp Repts 50-206/90-26,50-361/90-26 & 50-362/90-26 on 900625-29.No Violations Noted.Weaknesses Re Implementation of Internal Exposure Control Program Noted ML20055G5771990-07-17017 July 1990 Advises That New Storage Facility Meets Requirements of 10CFR73.21(d)(2) & Acceptable for Storage of Safeguards Info,Per 900403 Request ML20055D5201990-07-0202 July 1990 Requests Util Provide Ref Matls Listed in Encl for Requalification Program Evaluation & Exams During Wk of 901001,by 900801.Failure to Supply Ref Matl as Required May Result in Postponement of Exam ML20055F3871990-06-29029 June 1990 Forwards Insp Repts 50-206/90-22,50-361/90-22 & 50-362/90-22 on 900422-0602 & Notice of Deviation.Several Staff Members May Have Misunderstanding Re Licensee Ability to Make Repeated Entries Into & Exits from Tech Spec Statements ML20055D5361990-06-29029 June 1990 Discusses Electrical Safety Sys Functional Insp Conducted on 891030-1130 & Forwards Notice of Violation ML20055E1641990-06-28028 June 1990 Authorizes Use of Alloy 690 as Alternative to Alloy 600 in Steam Generator Tube Plugs,Per 900627 Request.Nrc Endorsed Use of Alloy 690 for Fabrication of Plugs in NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube.. ML20059M9701990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248E0851989-09-29029 September 1989 Forwards Amend 18 to Indemnity Agreement B-31 Re Changes to 10CFR140, Financial Protection Requirements & Indemnity Agreements, Effective 890701 ML20248J0561989-09-22022 September 1989 Forwards Insp Repts 50-206/89-26,50-361/89-26 & 50-362/89-26 on 890828-0901 & Acceptance Criteria.No Violations or Deviations Noted ML20248H9271989-09-20020 September 1989 Forwards Insp Repts 50-206/89-23,50-361/89-23 & 50-362/89-23 on 890814-18.No Violations Noted ML20248B5261989-09-19019 September 1989 Provides Info Re Generic Fundamentals Exam Section of Licensing Written Exam to Be Administered on 891004 ML20248B7841989-09-16016 September 1989 Advises That Portions of 880624 & 0825 Revs 19,19A & 20 to Physical Security Plan Consistent w/10CFR50.54(p) & Acceptable.Unacceptable Portion Withheld (Ref 10CFR73.21) ML20247B1181989-08-25025 August 1989 Forwards Insp Repts 50-206/89-18,50-361/89-18 & 50-362/89-18 on 890618-0729 & Notice of Violation ML20248A9121989-07-28028 July 1989 Advises of Reactor Operator Written Exams Scheduled for 891031 & Operating Exams Scheduled for 891101-03.Ref Matl Requirements for Reactor/Senior Reactor Operator Licensing Exams Encl ML20245G7031989-07-26026 July 1989 Forwards Insp Repts 50-206/89-14,50-361/89-14 & 50-362/89-14 on 890430-0617.No Violations Noted.Addl Example of LER Failing to Properly Address All Applicable Root Causes & Corrective Actions for Event Identified in Rept IR 05000206/19890171989-07-0606 July 1989 Forwards Safeguards Insp Repts 50-206/89-17,50-361/89-17 & 50-362/89-17 on 890619-23.No Violations Noted.Repts Withheld (Ref 10CFR73.21) ML20246B5701989-06-22022 June 1989 Forwards Enforcement Conference Repts 50-361/89-19 & 50-362/89-19 on 890602 & Notice of Violation.Importance of Prompt Corrective Actions for Identified Engineering Program Deficiencies Addressed During Conference ML20246L6911989-06-22022 June 1989 Forwards Exam Rept 50-361/OL-89-01 for Units 2 & 3 Administered on 890512.Candidate Failed to Meet Min Qualification Requirements for Licensing ML20245K3571989-06-16016 June 1989 Forwards Insp Repts 50-206/89-15,50-361/89-15 & 50-362/89-15 on 890508-26.No Violations Noted IR 05000361/19880351989-05-31031 May 1989 Confirms 890602 Enforcement Conference in Region V to Discuss Concerns Re Inoperability of Emergency Chillers Noted in Insp Repts 50-361/88-35 & 50-362/88-37,per 890524 & 31 Telcons.Agenda & Notice of Meeting Encl ML20246N6641989-05-15015 May 1989 Responds to Request to Revise Physical Security Plan,Section 5.1.1 Re Granting Unescorted Access to Protected Areas. Advises of Issuance of Rule Requiring All Power Reactor Licensees to Have Access Authorization Program ML20247G1391989-05-12012 May 1989 Advises That Evaluation of Requalification Program & Licensed Personnel Scheduled for Wks of 890814 & 28.Ref Matl Listed on Encl Should Be Furnished by 890616 ML20246P8861989-05-0202 May 1989 Forwards Insp Repts 50-206/89-08,50-361/89-08 & 50-362/89-08 on 890313-23 & Notice of Violation.Rept Describes Too Many Examples Involving Inadequate Control of Radioactive Matl ML20246C2441989-04-19019 April 1989 Forwards Insp Repts 50-206/89-12,50-361/89-12 & 50-362/89-12 on 890320-24.No Violations or Deficiencies Noted ML20236B8601989-03-13013 March 1989 Advises That 880204 & 890216 Revs 17 & 17A to Physical Security Plan,Respectively,Consistent W/Provisions of 10CFR50.54(p) & Acceptable for Inclusion in Plan IR 05000206/19890051989-02-28028 February 1989 Forwards Safeguards Insp Repts 50-206/89-05,50-361/89-05 & 50-362/89-05 on 890206-10.No Violations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20235T7991989-02-27027 February 1989 Advises That 871229,880204 & 890216 Revs 4A,5 & 5A, Respectively,To Safeguards Contingency Plan Acceptable ML20235Q6011989-02-10010 February 1989 Forwards Notice of Issuance of Amends to Licenses NPF-10 & NPF-15 & Opportunity for Hearing on 881024 Request Re Change to Tech Spec 3/4.8.1.1, AC Sources ML20235L0941989-02-0909 February 1989 Requests Encl Ref Matl Be Submitted by 890227 for Reactor Operator Licensing Exams Scheduled for 890505.Inadequate or Incomplete Ref Matl May Result in Exam Rescheduled ML20245C0771989-02-0808 February 1989 Identifies Addl Technical Issues Which NRC Must Resolve Before Restart from Current Refueling Outage ML20206M4061988-11-28028 November 1988 Denies 881112 Request for Commission to Extend Public Comment Period on Proposed Fitness for Duty Program ML20195H6681988-11-28028 November 1988 Responds to 881112 Request for Commission to Extend Public Comment Period on Proposed Fitness for Duty Rule.Comments Received After 881121 Will Be Considered If Practical ML20206L7571988-11-22022 November 1988 Informs That Review of Change Notice 29 to Topical Rept SCE-1-A, QA Program, Amend 11 Will Require More than 60 Days to Complete Review & Evaluation ML20206J5201988-11-16016 November 1988 Informs That 881108 Request for Extension of Public Comment Period on Proposed Fitness for Duty Rule Denied.Ample Response Time Provided IR 05000361/19880101988-11-0707 November 1988 Ack Receipt of 880902 & 1003 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/88-10 & 50-362/88-10 ML20206D0331988-10-31031 October 1988 Forwards Exam Rept 50-361/OL-88-02 Administered on 880726-0811.Rept for Both Units ML20205R6931988-10-26026 October 1988 Documents Change in Schedule for Administration of Reactor Operator & Senior Reactor Operator Licensing Exams.Written Exams Scheduled for 881213 & Plant Oral Exams on 881214-16 IR 05000361/19880151988-10-0404 October 1988 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/88-15 & 50-362/88-16 ML20154N9121988-09-0909 September 1988 Forwards Emergency Operating Procedures Insp Repts 50-361/88-13 & 50-362/88-14 on 880601-14.No Violations or Deviations Identified.Emphasizes Staff Commitment to Eliminate Deficiencies in Procedures & Training Program ML20154N9301988-09-0909 September 1988 Forwards Insp Rept 50-362/88-22 on 880718-0805 & Notice of Violation 1990-09-18
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217P7111999-10-26026 October 1999 Informs That Licensee 990330 Response to GL 97-06 Provides Reasonable Assurance That Condition of Licensee Steam Generator Internals Is in Compliance with Current Licensing Bases for Plant ML20217J8631999-10-15015 October 1999 Forwards Insp Repts 50-361/99-12 & 50-362/99-12 on 990808- 0918.One Violation Identified Involving Inoperability of Emergency Diesel Generator in Excess of Allowed Outage Time ML20217B5981999-10-0606 October 1999 Informs That Staff Concluded That All Requested Info for GL 98-01, Year 2000 Readiness in Us Nuclear Power Plants, Provided for San Onofre Nuclear Generating Station,Units 2 & 3 ML20216J2631999-09-28028 September 1999 Forwards Copy of Final Accident Sequence Precursor (ASP) Analysis of Operational Event at Songs,Unit 2,reported in LER 361/98-003 ML20212D9921999-09-16016 September 1999 Informs That on 990818,NRC Staff Completed Midcycle PPR of San Onofre.Nrc Plan to Conduct Core Insps & One Safety Issues Evaluation of MOVs at Facility Over Next 7 Months. Details of Insp Plan Through March 2000 Encl ML20217B9011999-09-10010 September 1999 Responds to Which Addressed Concerns Re Y2K Issue & Stockpiling of Potassium Iodide (Ki) Tablets by Informing That San Onofre Nuclear Station Already Completed All Work Required to Be Ready for Y2K Transition ML20211K4191999-09-0303 September 1999 Final Response to FOIA Request for Documents.Documents Listed in App a Being Withheld in Part (Ref FOIA Exemptions 5 & 7) ML20211N0261999-09-0303 September 1999 Forwards Exemption from Certain Requirements of 10CFR50.44 & 10CFR50,app A,General Design Criterion 41 in Response to Util Request of 980910,as Supplemented 990719 & SER ML20211H3321999-08-30030 August 1999 Discusses 1999 Emergency Preparedness Exercise Extent of Play & Objectives.Based on Review,Nrc Has Determined That Exercise Extent of Play & Objectives Are Appropriate to Meet Emergency Plan Requirements ML20211J7151999-08-27027 August 1999 Forwards Insp Repts 50-361/99-09 & 50-362/99-09 on 990627- 0807.Two Violations Being Treated as non-cited Violations ML20211H8561999-08-23023 August 1999 Forwards SE Accepting Licensee 970625 Requests for Relief RR-E-2-03 - RR-E-2-04 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20211J5821999-08-23023 August 1999 Corrected Copy of ,Changing Application Date from 970625 to 990625.Ltr Forwarded SE Accepting Licensee 990625 Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section XI as Listed 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 ML20210N9721999-08-10010 August 1999 Responds to Appeal of FOIA Request for Documents Re Osre Issue.No Osre Visit Scheduled for Sept 1996 at Plant,Per 990722 Telcon.V Dricks,In Ofc of Public Affairs Should Be Contacted Re Osre Issue ML20210N0901999-08-0909 August 1999 Informs That 990312 Application Requested Amends to Licenses DPR-13,NPF-10 & NPF-15,respectively,being Treated as Withdrawn.Proposed Change Would Have Modified Facility TSs Pertaining to SONGS Physical Security Plan 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 ML20210B9891999-07-20020 July 1999 Ack Receipt of Transmitting Plant Emergency Plan Implementing Procedure SO123-VIII-1, Recognition & Classification of Emergencies ML20209D8051999-07-12012 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, Issue on 950519 to Plant. NRC Revised Info in Reactor Vessel Integrity Database & Is Releasing It as Rvid Version 2 ML20209F5681999-07-0909 July 1999 Forwards Insp Repts 50-361/99-08 & 50-362/99-08 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation,Consistent with App C of Enforcement Policy ML20196K6721999-07-0202 July 1999 Discusses 990628 Meeting Conducted in Region IV Office Re Status of San Onofre Nuclear Generating Station Emergency Preparedness Program.List of Attendees & Licensee Presentation Encl ML20196K3351999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for San Onofre Unit 1 Will Be Transferred to Wc Huffman ML20212J3581999-06-24024 June 1999 Final Respons to FOIA Request for Records.App a Records Withheld in Part (Ref Exemptions 1 & 3) ML20209D7851999-06-16016 June 1999 Requests That San Onofre Nuclear Generating Station Be Included as One of Several Reference Plants in GSI-191 Study ML20195J6441999-06-15015 June 1999 Forwards Request for Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Response Requested within 30 Days of Receipt of Ltr ML20196A7351999-06-15015 June 1999 Requests That Cover Page to NRC Insp Repts 50-361/98-14 & 50-362/98-14 Be Replaced with Encl Page.Originally Issued Page,Signed by T Steka,Was Dated Incorrectly ML20207H4021999-06-14014 June 1999 Requests Addl Info Re Completion of Time for Containment Isolation Valves,Same as for Engineered Safeguards Features ML20196A8001999-06-0909 June 1999 Requests That Pages 14-17 of NRC Insp Repts 50-361/99-04 & 50-362/99-04 Be Replaced with Encl Pages.Initial Issued Rept Contained Some Duplicated Info ML20195E8001999-06-0808 June 1999 Forwards Insp Repts 50-361/99-06 & 50-362/99-06 on 990404- 0515.Violations Identified & Being Treated as Noncited Violations ML20195E8091999-06-0707 June 1999 Ack Receipt of Transmitting Licensee Emergency Plan,Rev 7 Under Provisions of 10CFR50.54(q) ML20195E8281999-06-0707 June 1999 Ack Receipt of Transmitting Licensee Emergency Plan Implementing Proceedure SO123-VIII-1,rev 11 Under Provisions of 10CFR50.54(q) ML20207E6521999-06-0202 June 1999 Responds to Ltr Which Identified Several Inaccuracies within NRC Insp Repts 50-361/98-18 & 50-362/98-18.Forwards Revised Pages for page-by-page Replacement in Insp Repts ML20195D2771999-06-0202 June 1999 Forwards Se,Concluding That Util Has Capability to Perform Reload Design & non-LOCA Analyses for Songs,Units 2 & 3, Based on Review of TR SCE-9801-P & Onsite Audit of Implementation of Reload Technology Transfer Program ML20207A8981999-05-25025 May 1999 Advises That Versions of SCE-9801-P,Rev 0 & CEN-635(S)-P, Rev 00,submitted in 981130 & s & Affidavits & 990225,marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20206U3681999-05-18018 May 1999 Forwards Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Matl Encl Contains Safeguards Info & Will Not Be Placed in PDR (Ref 10CFR2.790) ML20207A2131999-05-14014 May 1999 Submits Summary of 990422 Meeting in San Clemente,Ca Re PPR Results Completed 990211.Informal Discussions Held with Public Following Meeting Re Recent Changes Used to Assess Licensee Performance ML20206P1521999-05-13013 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Reorganization Chart Encl ML20206P4051999-05-12012 May 1999 Responds to Re Request of TS Interpretation. Instrumentation with Battery Backup,But Lacking DG Backup Cannot Be Excluded from Provisions of Action B.2 ML20206Q2481999-05-10010 May 1999 Forwards Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted ML20206H4881999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Aswer Key,Encl for Info.Without Encl ML20206H7651999-05-0606 May 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 on 990416. Two Operators & Two Senior Operators Were Evaluated.Four Applicants Satisfied Requirements of 10CFR55 & Appropriate Licenses Issued IR 05000361/19983021999-05-0303 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-361/98-302 & 50-362/98-302 Issued on 990104.Review Found Reply Responsive to Concerns Raised ML20206K5061999-04-30030 April 1999 Discusses Closure of OI Investigation 4-1998-04 Re Southern California Edison Led Joint Util Audit of Inst of Nuclear Power Operations Fitness for Duty & Access Authorization Programs.Synopsis from Subj Rept Encl ML20206B4921999-04-20020 April 1999 Forwards Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Occurred & Being Treated as non-cited Violations ML20205S2941999-04-20020 April 1999 Forwards RAI Re Licensee 981230 Request to Implement risk-informed IST Program During Remainder of Second 10-year Interval for SONGS & to 970313 Response to GL 96-05 ML20206B4241999-04-20020 April 1999 Forwards Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of NRC Enforcement Policy ML20205Q6171999-04-19019 April 1999 Forwards SE Authorizing Licensee 980826 Request for Relief from ASME B&PV Code,Section XI Requirements for Certain ISIs at Plant,Units 2 & 3 ML20205R0101999-04-16016 April 1999 Discusses Request for Approval of Deviation from Approved Fire Protection Program.Forwards SE Related to Request for Approval Incorporating Certain Requirements of App R to 10CFR50 ML20205M9421999-04-13013 April 1999 Forwards Emergency Response Data System Implementation Documents.Data Point Library Updates for Kewaunee (271), San Onofre (272) & Clinton (273) Encl.Also Encl Plant Attribute Library Update for Grand Gulf (274).Without Encls ML20205M9891999-04-0707 April 1999 Informs That L Raghavan Assumed Project Manager Responsibilities Effective 990329 & Dembek Assumed Responsibilities as Section Chief for SONGS ML20205E5441999-03-30030 March 1999 Forwards Insp Repts 50-361/99-01 & 50-362/99-01 on 990103- 0220.Three non-cited Violations Were Identified 1999-09-03
[Table view] |
Text
.
. l
. o .. .
007 - 4 1988 Docket Nos. 50-361, 50-362 Southern California Edison Company P. O. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Attn: Mr. Kenneth P. Baskin, Vice President Nuclear Engineering, Safety, and Licensing Department Gentlemen:
Thank you for your letter of September 12, 1988, in response to our Notice of Violation and Inspection Report No. 50-361/88-15 and 50-362/88-16, dated August 12, 1988, informing us of the steps you have taken to correct the items which sie brought to your attention. Your corrective actions will be verified during a future inspectio Your cooperation with us is appreciate
Sincerely,
R. erman, Chie Reactor Projects Branch bec w/ copy of letter dated 9/12/88: ,
Resident Inspector Project Inspector G. Cook A. Johnson B. Faulkenberry J. Martin Docket File LFMB State of California l l
bec w/o copy of letter dated 9/12/88:
M. Smith u rg JTa M A
- sin RZ Nan 10/ /88 10/ t//88 10/([/88 10/f/88 1f/88 ern ;mm . ;mm V V v e r wro v v j TO POR '
ES / No .1 i\ \
$0bb? $$$@@jg /
PDC
. .. .t..
, , ee *
- .
'
- s Southem Califomla Edison Co any P. O. BO X 800 g ,
2244 WALNUT GROVE AVENUE ROS EM EAD. CALIFORNIA 91770 v'C E P t et sie 308 01 September 12, 1988
!
.
U. S. Nuclear Regulatory Commission'
Attention: Document Control Desk Hashington, D.C.' 20555 -
Gentlemen:
Subject: Docket Numbers 50-361 and 50-362
'
Reply to a Notice of Violation and Notice of Deviation San Onofre Nuclear Generating Station Units 2 and 3 Reference: Letter, Hr. J. B. Hartin (NRC) to Mr. Kenneth Baskin (SCE), dated August 12, 1988-l l
The above referenced letter forwarded NRC Inspection Report Nos. 50-361/88-15 l and 50-362/88-16, a Notice of Violatio.1 and a Notice of Deviation resulting l from the routine inspections conducted by Hessrs. F. R. Huey, J. E. Tatum, A. L. Hon, and A. D. Johnson during the period May 22 through July 2,198 In accordance with 10 CFR 2.201, Enclosures A and B to this letter provide the Southern California Edison (SCE) reply to the subject Notice of Violation and
,
Notice of Deviation, respectivel j
!
If you require any additional information. please so advis Very truly yours, S4 h J Enclosures: as stated cc: J. 8. Hartin, Regional Administrator, NRC Region V F. R. Huey, NRC Senior Resident Inspector, San Onofre Units 1, 2 and 3
.f2rtru g, s 01.nnm.- f lf <
'
- - .
. . ..
t
'
ENCLOSURE A REPLY TO THE NOTICE OF VIOLATION
.
Appendix A to Mr. J. B. Hartin's letter, dated August 12, 1988, states in part:
"10 CFR Part 50, Appendix B, Criterion V provides, in part, that:
' Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.'
"Chapter SC (Revision 10) of the. licensee's TQAM, paragraph 8 . states only measuring and test equipment evidencing a current calibration status shall be used for safety related activitie "Paragraph 6.13.2.4 of Haintenance Procedure S0123-I-1.7 (TCN 2-2) states that the journeyman shall draw and inspect all measuring and test equipment to be used for the activity to ensure that the calibration date will remain valid for the duration of the activity, and shall record the instrumentation used on the maintenance order (HO).
"Contrary to the above requirements:
" On June 17, 1988, a strip chart recorder (H&TE #I2,9097) with a calibration due date of June 16, 1988, and a D. C. amplifier (H&TE #I2-8696) with a calibration due date of June 14, 1988, were being used to gather data to evaluate operability of the post-LOCA hydrogen monitoring system (Train B).
" The measuring and test equipment being used to evaluate the operability of the post-LOCA hydrogen monitoring system (Train B) was not recorded on the applicable H0, No. 8806060 "This is a Severity Level IV violation (Supplement I)."
RESPONSE Reasons for the violation, if admitted SCE admits that contrary to procedure $0123-I-1.7, "Maintenance Order Preparation, Use And Scheduling " (A) measuring and test equipment (H&TE) was used which had expired stickerst and (8) the H&TE was not recorded on the maintenance order. SCE's investigation has established that there is no safety significance to this even The facts and circumstances surrounding each of these issues are as
, follows:
.
,_ .---,--.n.-- - - - - - - - - - . - , - .
,- , .- - - - , , _ . - - - ,
a .. . ..
. . .. .
o
, -2-
. Use of H&TE with Expired Calibration Stickers SCE's investigation determined that the strip chart recorder -
and the DC amplifier were attached to the Train 8 post-LOCA hydrogen monitoring system to collect investigative information on June 8, 1988. When the I&C technician attached the strip chart recorder and the DC amplifier to the hydrogen monitoring system, he verified that their calibration stickers had not expired. He was aware that on or before the calibration due dates, they should be returned for calibration in accordance with the Station's H&TE recall progra However, due to the in'vestigative nature of the activity, it was not known and therefore not specified in the H0 as to how
,long such information gathering would las The H&TE was left connected to the Hydrogen Monitoring System beyond the calibration due dates. The investigative information obtained on the Train 8 post-LOCA hydrogen monitor was not used to evaluate operability in accordance with Technical Specification surveillance requirements. Instead, the information gathered with this equipment was used by the cognizant engineer to develop potential corrective action Subsequent to these actions, Technical Specification operability surveillances were performed using M&TE within the required calibration due date In summary, personnel error, exacerbated by the open-ended nature of the investigative activity, resulted in the use of the H&TE two days beyond its calibration due dat Notwithstanding this, the information gathered by the equipment was not used as the basis for determining operabilit i H&TE Not Recorded on H0 !
Procedure S0123-I-1.7 is the general procedure governing the maintenance order control process. This procedure requires that the H&TE used be documented on the H0. In addition, procedures 50123-II-1.0, "Calibration And Control of Measuring And Test Equipment," and S0123-II-1.2, "Preparation and l
Responsibility of the M&TE Traveler," require that when H&TE is issued, a corresponding H&TE traveler is also issued to record i i
the activities (maintenance order, construction work order, !
etc..) for which the M&TE is used. These two procedures provided guidelines under which an H&TE could be considered
"Not Used" and be recorded as such on the H&TE traveler. The
,
technician erroneously believed that these guidelines provided the applicable guidance for recording "None" under the "Test l Equipment /Special Tools Used" section of H0 8806060 i
- _ . . _ - . - - - - - , - - -
i .. . ..
. . . ~
'
-3-
.
In summary, contrary to procedure S0123-I-1.7, the strip chart recorder and the DC amplifier used were not recorded on H0 88060605. This was caused by procedural ambiguity within and between procedures governing the work activitie . Corrective steps that have been taken and the results achieved On June 17, 1988, the strip chart recorder and the DC amplifier were removed from the Train 8 post-LOCA hydrogen monitoring syste This event was discussed with all appropriate Units 2/3 I&C technician To be consistent with proced'ure S0123-I-1.7, which requires that all H&TE used be recorded in the H0, procedur6s 50123-II-1.0 and S0123-II-1,2 have been revised to require that all activities for which the H&TE is used, be recorded in the H&TE travele .
Corrective actions that will be taken to avoid further violations Regardless of the nature of the activities involved, the use of H&TE with a current calibration sticker is a matter of station policy and is required by station procedures. Clearly, the use of the H&TE with expired calibration stickers was contrary to the station policy and procedures. It is SCE's position to require the use of H&TE with a current calibration sticker. Consequently, a reading assignment, describing this event and emphasizing the need to verify that no H&TE will be used beyond its calibration due date, will be distributed to appropriate maintenance personne Future investigative maintenance activities of indeterminate duration, which involve the use of M&TE, will include administrative controls to enhance the consideration given by technicians to the calibration due dates vis-a-vis the expected completion of the investigative effor These corrective actions are expected to be completed by-November 15, 198 . Date when Tull compliance will be achieved Full compliance was achieved on June 17, 1988, when the H&TE with the expired calibration stickers was remove F
.
- - - _ . - - - . - - - - - .. .. - - - . - .
i , .
,
. . -
f ENCLOSURE B REPLY TO THE NOTICE OF DEVIATION Appendix B to Mr. J. B. Hartin's letter, dated August 12, 1988, states in part:
"Paragraph 9.1.2.2 of the Updated Final Safety Analysis Report (Revision 4) for San Onofre Nuclear Generating Station Units 2 and 3 states: 'All connections to the spent fuel storage pool are made as to preclude the possibility of siphon draining of the pool.'
"Contrary to the above, the fuel pool purification suction piping (015-4"-J-LLO) was found on June 22, 1988, to extend to the bottom of the spent fuel storage pool, and system features did not preclude the possibility of siphon draining of the pool."
RESPONSE Reasons for the deviation, if admitted SCE admits that the June 22, 1988 system alignment of the spent fuel storage pool draining of thepiping pool.did not preclude the possibility of siphon The design of the spent fuel storage pool was completed in 197 In
'
preparing the design to preclude the possibility of siphon draining of the pool, SCE utilized Section 9.1.1 of the NRC Standard Review l Plan which permits either the use of siphon breakers / check valves or other devices such as locked valves coupled with administrative controls preclude (procedures governing a siphon even < the use of the locked valves), to i
In the case of the spent fuel storage pool purification line, a '
combination of locked closed valves and administrative controls were I intended to prevent inadvertent siphoning (notwithstanding that under certain circumstances the spent fuel pool skimmers may currently function as a siphon breaker). Valves HUO76 HU100, and HU101 were designated as locked closed valves. The Piping3 and Instrumentation Drawings (P& ids) were subsequently issued showing these as locked closed valve No basis was provided in the design documents which explained the
,
' necessity for locking these valves closed. Consequently, when a revision to the Operations procedure S023-3-2.8.1, "Refueling Cavity Draining Operation", was prepared, the design intent of these valves was not fully understood, s
.
s .;>* .
.% ~
., .
r-2-In addition, the Final Safety Analysis Report (FSAR), Section 9.1.2.2, description of the spent fuel storage pool and cooling systems cited above does not provide a complete description of the
.
design, including the use of administrative control . Corrective steps which have been taken and the results achieved Updated design information regarding administrative controls for the spent fuel storage pool piping and valves has been provided to appropriate personne Procedures regarding the operation of the spent fuel storage pool piping and valve alignments.have been revised to include appropriate '
precautions and controls to prevent potential future siphon alignment . Corrective steps which will be taken to avoid further deviations A design modification is being evaluated to deter'mine the feasibility and cost of a change to the system design to physically preclude the establishment of a sipho FSAR Section 9.1.2.2, "Spent Fuel Pool and Cooling Systems" will be revised at the next annual revision to describe the current design i and the use of administrative control Licensee Event Report (LER) number 88-017 (Docket No. 50-361),
reported the siphoning event of Junt 22, 1988. As discussed in the ,
LER, a revision to the LER is being prepared which will include the above corrective action .-
4. The date when corrective action will be completed The revisions to applicable Operating procedures were completed on September 7, 198 F
!
.
l
.
,---
. - - - - - -- - - - - - - - . --. , - ~ - . , , , - - , .,. , , , ---, ,. - - , - - ,