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| {{Adams | | {{Adams |
| | number = ML20196A562 | | | number = ML20238A790 |
| | issue date = 01/28/1988 | | | issue date = 08/20/1987 |
| | title = Ack Receipt of 871221 Ltr Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-293/87-33 | | | title = Insp Rept 50-293/87-33 on 870803-07.Violations Noted.Major Areas Inspected:Post Mod Test Program Preoperational Test Procedure Review,Qa/Qc Interface w/post-mod Testing, Independent Verification & Plant Tours |
| | author name = Johnston W | | | author name = Briggs L, Eselgroth P |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| | addressee name = Bird R | | | addressee name = |
| | addressee affiliation = BOSTON EDISON CO. | | | addressee affiliation = |
| | docket = 05000293 | | | docket = 05000293 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8802050094 | | | document report number = 50-293-87-33, NUDOCS 8708310211 |
| | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE | | | package number = ML20238A760 |
| | page count = 3 | | | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS |
| | | page count = 6 |
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| JAN 281988
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| Docket No. 50-293
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| . Boston Edison Company ATTN: Ralph G. Bird - | | ,*- |
| Senior-Vice President - Nuclear 800 Boylston Street Boston, Massachusetts 02199 Gentlemen:
| | U.S. NUCLEAR REGULATORY COMMISSION , |
| Subject: Inspection-No. 50-293/87-33 This refers to your letter dated December 21, 1987, in response 'to our letter dated August 21, 1987.
| | REGION I l Report.N /87-33 |
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| | . Docket N License N DPR-35 Licensee: Boston Edison Company M/C Nuclear 800 Boylston Street-Boston, Massachusetts 02199 Facility Name: Pilgrim Nuclear Power Station Inspection At: Plymouth, Massachusetts .I |
| | . Inspection Conducted: August- 3-7, 1987 1 i |
| | j Inspectorsi ~ 4M L. Briggs, laid Reactor Engineer, DRS 8 /.s70 / # 7 date Approved by: / J , 'f 82d[<f 7 P.'Eselgr ' , Chief, Test Programs Section / ddte 08, DRS j Inspection Summary: Inspection on August 3-7, 1987 (Inspection Report i No. 50-293/87-33) |
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| | Areas Inspected: Routine unannounced inspection of the licensee's post I modification test program preoperational test procedure review, QA/QC interface with post modification testing, independent verification and plant tour Results: One violation was identified for failure to adequetely review a design package and its associated post maintenance preoperational test, , l Paragraph ! |
| | Note: For acronyms not defined refer to NUREG-0544 " Handbook of Acronyms and l Initialisms". j l |
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| | 8708310211 870821 PDR ADOCK 05000293 G PDR |
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| Thank you for informing us of the corrective and preventive actions documented in your letter. These actions will be examined during a future inspection of your licensed program.
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| Your cooperation with us is appreciated.
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| | DETAILS A" |
| | '1.'0''PersonsContactfdc |
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| | * M.'Akhtar,< Modifications Management Group Leader |
| | * T. Beneduci, Senior Engineer, Modifications Management |
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| | * N. Brosee, Outage Manager- |
| | * R.,Grazio, FieM Engineering Sectinn Manager |
| | * P. Hamilton, Cortpliance Group Leader |
| | , ' * S, Hudson," Operations'Section Manager- |
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| | ' B. Lunn, Compliance Engineer |
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| | " J..Mattia, QA, Group Leader |
| | ' * A. Morisi,- @ pt and Turnover Section Mantger |
| | >2 l * K. Roberts, Station Nnager i |
| | *.R. Schifone, QA k NRC , |
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| | *fN. Blumburg, Chief, Operational Programs'Section |
| | * J. Lyash, Resident Inspector The inspector also contacted other memebers of the licensee'4 QA/QC and-technical stat ; |
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| | * Denotes those present at the August 7, 1987, exit meetin ~ |
| | 2.0' Post Modification Preoperational Testing (PMPT). Procedure Review l 2.1 Scooe |
| | ./ The PMPT's and Plant Design Changes (PDC's) listed below were |
| | " 4 a' reviewed in preparation for test witnessin The PMPT's were j ' reviewed for, technical and administrative adequacy and for |
| | . ,. f, , verification that testing is planned to adequately satisfy a regulatory svidance and licensee commitment They were also |
| | , reviewed to vsrify licensee review and approval, proper format, test F |
| | ' objectives, prerequisites, initial conditions, test data recording requirements and system return to normal. The PDC's were reviewed to determine what changes were made to the associated system and to provide a bases for the determination of PMPT scope necessary to s verify the system's modified desig 'f |
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| | PDC 86-70, Standby Gas Treatment System Modification; j |
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| | PDC 82-25, 011 and Vibration Alarms Modification on ) |
| | Recirculation Pump Motors; |
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| | PDC 85-59, HPCI Exhaust Vacuum Breaker; |
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| | TP 87-128, Pre-Operational Test of Standby Gas Treatment System Modification Per PDC 86-70, Revision 1, dated July 20, 1987; r |
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| Sincerely, RCRGT M. T.'.o
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| William V. Johnston, Acting Director Division of Reactor Safety
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| K. P. Roberts, Nuclear Operations Manager Paul Levy, Chairman, Department of Public Utilities Chairman, Board of Selectmen Plymouth Civil Defense Director l J. D. Keyes, Boston Edison Regulatory Affairs and Programs l E. D. Robinson, Nuclear Information Manager l R. N. Swanson, Nuclear Engineering Department Manager ,
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| The Honorable E. J. Markey '
| | TP 86-95, Pre-Operational Test.of Oil Level and Vibration System on the Recirculation Pumps, Revision ~1, dated June 11, 1987;'and, |
| Senator Edward P, Kirby The Honorable Peter V. Forman Sharon Pollard, Secretary of Energy Resources l Peter W. Agnes, Assistant Secretary of Public Safety,
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| | TP.87-88, HPCI. Vacuum Breaker Pre-Operational Test, Revision 0 1, (draft). |
| Commonwealth of Massachusetts Rachel Shimshak, MASSPIRG y
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| Public Document Room (PDR)
| | 2.2 . Discussion During the review of TP 87-128 the inspector noted several areas of the. test procedure that were either in error or. did not' appear. to verify the design of the modified system. These items were discussed with one of the licensee's senior Modifications Management Group (MMG) engineer The' engineer and licensee management agreed with the inspector that the following errors / omissions should tave been identifie Paragraphs 7.'2.5, 7.3.5 and 7.4.5 required 5 damper control switches- to be in the. auto position and their associated dampers in the open position. The associated dampers would be in the closed position with'the specified switch position and no initiation signal present, Section 7.3.8.and 7.3.8.9-did' not require verification tha't. |
| Local Public Document Room (LPDR)
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| Nuclear Safety Information Center (NSIC)
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| NRC Resident Inspector Commonwealth of Massachusetts (2)
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| 0FFICIAL RECORD COPY RL PILGRIM 87-33 - 0001.0.0 01/11/88 .I i 8802050094 88012e PDR y0i 'I
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| O ADOCK 05000293 PDR j m - J
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| Boston Edison Company 2
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| Region I Docket Room (with concurrences)
| | valve A0N-112 closed when the 'B'. Standby' Gas Treatment System-(SBGTS)-fan tripped (per procedure). Inlet valve A0N-106 was verified as closin Paragraph 7.3.8.6 required the differential pressure across the calibrated orifice plate'(DPI-AA-32) in the 'B' SBGTS train to be recorded with the 'B' SBGTS fan in standby (off). This reading was being taken to measure 'B' train bypass flow so it could be combined with 'A' train to determine system flo Under the system conditions specified this reading would be zero , |
| Management Assistant, DRMA (w/o enc 1)
| | (0) since one of the SBGTS modifications moved the upstream i bypass flow connection such that the connection between the A , |
| Section Chief, DRP R. Wessman, PM, NRR PA0 (2) SALP Reports Only Robert J. Bores, DRSS S. J. Collins, DRP
| | and B SBGTS trains is now downstream (bypassing) of the l' |
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| | calibrated orifice plat The flow recorded on the 'A' |
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| | calibrated orifice plant would represent full system flow ter , |
| RI:DRSh[ RI S , RS Briggs 79cb Ke ilo
| | the specified lineu ~ Train 'B' logic requires A0N-106 damper (inlet) to open and ' |
| / | | pick up a position limit switch which allows the 'B' SBGTS fan to start and outlet damper A0N 112 to open. This logic sequence would occur during any start of the 'B' SBGTS train and was not- ; |
| 1//j/88 1/2,\/88 1 88 0FFICIA RECORD COPY RL PILGRIM 87-33 - 0002.0.0 01/11/88
| | checked in TP 87-12 The procedure did'not verify that per design the 'B' SBGTS i train would remain running after 20 minutes if the 'A' train |
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| g sosrmmsm Executive Offices 800 Boylston street Boston, Massachusetts o2199.
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| Ralph G. Bird December 21', 1987 senior Vice President - Nucle at BECo 'Ltr. #87 202
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| .U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293 Subject: NRC Inspection Report 50-293/87-33
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| ==Dear Sir:==
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| Attached is a revision of Boston Edison Company's response (BECo Ltr. #87-176, October 5,1987) to the Notice of Violation contained in the subject inspection report. Our response is revised as a result of clarifications obtained during a telephone conference between Boston Edison Company and NRC representatives on November 10, 1987.
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| Subsequent to the NRC Inspection 87-33, multiple communications with the NRC inspector occurred at our request.
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| These communications were necessary because inspection. we did not effectively communicate our position during the The need for effective communication and diligence in )
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| investigating the appropriate inspectors'
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| membersconcerns in a timely manner has been reemphasized to of our staff.
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| Please do not hesitate to contact me directly if you have any questions.
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| .G. Bird 1 BPL/la Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Sr. Resident Inspector
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| . . ATTACHMENT
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| Boston Edison Company Docket No. 50-293 Pilgrim Nuclear Power Station License No. OPR-35 Notice of Violation 10CFR50.54 (a)(1), requires each nuclear power plant licensee subject to the Quality Assurance Criteria in 10CFR50, Appendix B, to implement pursuant to 10CFR50.34(b)(6)(ii), the quality assurance program described or referenced in the Safety Analysis Report, including changes to that report.
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| Boston Edison Company Quality Assurance Manual (BEQAM) Volume II implements the requirements of 10CFR50, Appendix B. BEQAM, Section 6, Document Control, requires that measures be established to assure that documents affecting quality are reviewed for adequacy and approved for release by authorized personnel.
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| Contrary to the above on August 6,1987, it was determined that Plant Design Change (PDC) 86-70, Standby Gas Treatment System Modification, had been reviewed, released and implemented but did not completely specify design verification testing requirements as required by BEQAM, Section,3, Paragraph 3.3.2.8., specifically electrical functional and logic testing requirements.
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| In addition, Temporary Procedure 87-128, Preoperational Test of Standby Gas Treatment System (SBGTS) Modification Per PDC 86-70 was reviewed, approved and released for performance on July 22, 1987 and contained several errors and did not verify all design aspects of PDC 86-70. Specifically, neither the formal l review process of PDC 86-70, nor the formal review of TP 87-128 identified the missing testing requirements of the PDC or the failure of the TP to fully l verify the SBGTS modified design. l Resoonse Discussion:
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| On November 10, 1987, Boston Edison Co. management personnel contacted NRC Region I management personnel via telecon to provide further explanation of the position described in our initial response to the Notice of Violation dated October 5, 1987. This dialogue enhanced our understanding of the basis for the Notice of Violation.
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| He concur with the inspector's general concerns regarding the adequacy of reviews and the need to more completely specify preoperational testing requirements in Plant Design Change packages. During the telephone conference, however, it was agreed that the perceived errors in TP87-128, identifled in Sections 2.2.B", 2.2.0 and 2.2.E'of the Inspection Report, were not errors. Although it was agreed that the error identified in Section 2.2.A of the inspection report would have been identified during the conduct of the test, it was also agreed that errors of this nature could be eliminated by a more thorough technical review. Agreement was not achieved regarding the perceived error identified in Section 2.2.C"of the Inspection Report, as we continue to believe that a cognizant inclusion of an unnecessary procedural step is not an error.
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| ATTACHMENT 1 (Cont.)
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| , The errors in TP 87-128 were identified by the inspector prior to the implementation of the preoperational test. During the conduct of a preoperational test, the test is halted if a discrepancy is identified.
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| The discrepancy must be resolved and the procedure reviewed prior to.
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| continuing the test. This conservative testing philosophy, in combination with the multiple levels of review and verification associated with the plant modification process, provide assurance against the possibility of errors in the final product. However, we recognize that the propensity to rely on the process, as opposed to assuring that the job is done right at each step in the process, must be guarded against.
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| The errors identified in TP87-128 were a result of a lack of a thorough technical review by independent reviewers. These reviews may have resulted from a substantial increase in individual work load in support of the plant outage. In particular, procedure reviewers are normally selected from the line organization based on their technical expertise.
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| These line organization reviewers have concurrent managerial and/or technical responsibilities. Although the need to take the time to do the job right the first time has been repetitively communicated by senior BECo management, a cituation of conflicting priorities may have resulted in a less thorough preoperational test review than desired.
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| The incomplete specification of electrical functional and logic testing requirements in PDC 86-70 resulted from a lack of procedural definition or other guidance regarding the level of detail required to be specified in a PDC. Because of this lack of guidance, the level of detail of testing requirements specified in PDC's has been inconsistent. He believe this situation developed in part because of the demonstrated ability of the Modification Management Group's personnel to prepare preoperational tests with limited direction from the Nuclear Engineering Department.
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| Corrective Actions Taken:
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| The Nuclear Engineering Department issued Technical Quality Memo (TQM) No. 92 on August 19, 1987 to reemphasize to engineering personnel the responsibility to clearly specify testing and acceptance requirements in Plant Design Change packages.
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| The Design Review Board (DRB) members have been specifically reinstructed concerning their responsibility to assure PDC packages contain complete preoperational testing requirements. The DRB members are comprised of the engineering discipline Group Leaders who are responsible for the performance of engineers performing design functions for Pilgrim Nuclear Power Station.
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| Temporary Procedure (TP) 87-128 has been revised to correct the identified discrepancies. TP87-128 Revision 3 was completed on August 29, 1987.
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| . ATTACHMENT 1 (Cont.)
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| The Modifications Management Group of the Nuclear Operations Department has established a three man team to conduct independent reviews of the preoperational test for the duration of RF0 No. 7.
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| This review tean has no other concurrent responsibilities and '
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| provides additional assurance that the large number of modifications implemented during RF0 No.7 receive thorough reviews.
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| As comitted in TQM No. 92, NED procedures will be revised to specify
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| - | | p h-l had. insufficient flow or.was tripped with the 'B'. train in standby, The system is designed to trip the 'B' train after 20 minutes if sufficient flow exist The inspector discussed the above items with the licensee and reviewed the other TPs and PDCs identified in Paragraph 2.1 abov It_was. observed that the other PDCs provided a more defined level of testing requirements. PDC 86-70 did not specify any electrical or logic checks while PDC 85-59 and 82-25 did. The inspector noted that the Boston Edison Quality Assurance Manual-(BEQAM) Paragraph 3.3. and 3.3.2.8 specifically requires the cognizant design organization, in this case Boston Edison Nuclear Engineering Department (NED), to specify acceptance criteria and methods for verifying' design changes, |
| A process is being developed (proceduralized) to require comments from the station review of PDC packages to be collected by the ;
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| Modification Management Group and sent to the Nuclear Engineering 1 Department (NED) for disposition prior to approval by the Operations l Review Committee. This process will provide feedback to the NED on PDCs released to the station.
| | such as qualification testin It was also noted that the Modifications Management Work Instruction Manual (MMWIM), dated January 12, 1987, in Section 10 requires the Maintenance Modification Group (MMG) to determine preoperational |
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| The results of the three man team's independent review of the !
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| preoperational tests prepared during RF0 No. 7 will be evaluated to I allow incorporation of lessons learned to the preoperational test review process if appropriate.
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| Date of Full Compliance: j Full compliance was achieved on August 29, 1987 when TP87-128 Revision 3 l was completed.
| | testing (POT) requirements and to prepare POTS to satisfy all aspects of required testin The inspector also observed that throughout the. entire review chain for this' PDC and TP that these deficiencies (lack of specified testing required to verify design and PMPT errors) were not identified and corrected. The licensee as part of their immediate correc+ive action statect that an independent, 3 man review group will be established, with no concurrent duties, to review PMPT's initiated for implementation during this outage . |
| | The review of the remaining PMPT's did not'ider.tify any procedural deviations from the system design as described in the PD .3 Findings The above examples relative to PDC 86-70 and TP 87-128 constitute a violation of the requirements of 10 CFR 50 Appendix B, Criterion VI and BEQAM, Section 6, Document Control, for failure to perform an adequate review (293/87-33-01). |
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| | 3.0 QA/QC Interface with Post Modification Testing 3.1 Scope The inspector requested all QC inspection reports (QCIR) associated with PDC 86-70 (SBGTS) and 82-25 (Recirculation Pump) which were implemented under maintenance requests 87-48-12 (SBGTS) and 86-2-49 j and 86-2-50 (Recirculation Pump). The following QCIR's were j provided the inspector. They primarily deal with the installation of i the modifications since testing of the modifications were in the l very early stages during this inspection, i |
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| I BOSTON EDISON \
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| 300 BWsty street
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| Ralph G. Bird October 5, 1987 semor Vice Presioent - Nuoear BECo Ltr. #87-176 l U.S. Nuclear Regulatory Commission Attention: Document Control Desk Hashington, DC 20555 License No. DPR-35 Docket No. 50-293 Subject: NRC Inspection Report 50-293/87-33
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| ==Dear Sir:==
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| Attached is Boston Edison Company's response to the Notice of Violation contained in the subject inspection report.
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| Based upon our review and investigation of the matters described in the subject inspection report, we do not believe a Violation is appropriate. The basis for this position is described in the Attachment to this letter. A meeting with the appropriate level of NRC management has been requested to allow further explanation of our position and the reasons we believe that the Notice of Violation should be withdrawn.
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| Please feel free to contact either myself or Mr. Robert Grazio (Telephone 617-747-8189) if you have any questions.
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| [R.G. Bird
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| $Q BPL/la Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Sr. Resident Inspector
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| ATTACHHEMI Boston Edison Company Docket No. 50-293
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| Pilgrim Nuclear Power Station License No. DPR-35 Notice of Violatiqn 10CFR50.54 (a)(1), requires each nuclear power plant licensee subject to the Quality Assurance Criteria in 10CFR50, Appendix B, to implement pursuant to 10CFR50.34(b)(6)(ii), the quality assurance program described or referenced in the Safety Analysis Report, including changes to that report.
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| Boston Edison Company Quality Assurance Manual (BEQAM) Volume II implements the requirements of 10CFR50, Appendix B. BEQAM, Section 6, Document Control, requires that measures be established to assure that documents affecting quality are reviewed for adequacy and approved for release by authorized personnel.
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| Contrary to the above on August 6, 1987, it was determined that Plant Design Change (PDC) 86-70, Standby Gas Treatment System Modification, had been reviewed, released and implemented but did not completely specify design verification testing requirements as required by BEQAM, Section 3, Paragraph 3.3.2.8., specifically electrical functional and logic testing requirements.
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| In addition, Temporary Procedure 87-128, Preoperational Test of Standby Gas Treatment System (SBGTS) Modification Per PDC 86-70 was reviewed, approved and released for performance on July 22, 1987 and contained several errors and did l not verify all design aspects of PDC 86-70. Specifically, neither the formal review process of PDC 86-70, nor the formal review of TP 87-128 identified the missing testing requirements of the PDC or the failure of the TP to fully verify the SBGTS modified design.
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| Resoonse Boston Edison believes that Plant Design Change (PDC) 86-70 and Temporary Procedure (TP) 87-128 were prepared, reviewed, approved, released and implemented in compliance with the requirements of 10 CFR Part 50, Appendix B and the Boston Edison Quality Assurance Manual (BEQAM). He have, however, implemented actions described at the end of this response to further strengthen the PDC testing process.
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| Discussion:
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| The subject Notice of Violation identifies three issues as follows:
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| 1. PDC 86-70 did not completely specify design verification testing requirements as required by BEQAM, Section 3, Paragraph 3.3.2.8, specifically, electrical functional and logic testing requirements.
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| 2. TP 87-128 contained several errors and did not verify all design aspects of PDC 86-70.
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| ATTACHMENT (Centd
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| 3. The review requirements of 10CFR50, Appendix B and SE0AM Volume II, Section 6, Document Control were not fully implemented as
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| evidenced by issue (1) and (2) above.
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| The balance of this discussion is formatted to address each of these issues.
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| Issue 1 - Design Verification Requirements:
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| Qualification testing is one of the BEQAM approved methods for performing design verification, but was not chosen for PDC 86-70.
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| Instead, PDC 86-70 was verified using the design review method as permitted by the BEQAM.
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| The PDC received multiple levels of review and approval including independent, interdisciplinary and Quality Assurance Department reviews and approvals. In addition, calculations were made and independently reviewed to support the design. The multiple reviews and calculations verified the adequacy of the design and satisfied the requirements of BEQAM Paragraph 3.3.2.8. The reviews and calculations are documented in the PDC package. Qualification testing was not used as a verification method for this PDC.
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| Our plant design change procedures require that preoperational test requirements and acceptance criteria are specified in the PDC. The preoperational test TP 87-128 was prepared to verify the functions of the SBGTS for the different modes of operation. The requirements of Section 3.3.2.8 of the BEQAM do not apply to TP 87-128 since it is not a design verification test.
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| Section 10.4.2.27 of the work instruction for PDC 86-70 specifies the testing requirements for the logic portion of the PDC and identifies the required calibrations. Sections 10.5.19 and 11.4 of the work instruction specified the acceptance tests required for electrical equipment. The level of detail specified in these sections of the PDC was adequate to assure that the SBGTS functions were verified.
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| :1 Issue 2 - Alleged Errors Our responses to the specific discrepancies identified in Section 2.2 of the Inspection Report follow.
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| Section 2.2.A states,
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| "Paragraphs 7.2.5, 7.3.5 and 7.4.5 required 5 damper control switches to be in the auto position and their associated dampers in the open position. The associated dampers would be in the closed position with the specified switch position and no initiation signal present."
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| Response:
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| Although the procedure was in error as stated the errors would have been identified during the conduct of the test as follows:
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| If the dampers were wired correctly, discrepancies between the observed damper positions and the damper positions specified in TP 87-128 would have been apparent.
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| ATTACHMENT (Cont.)
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| Only two of the five dampers were affected by the modi fication. If those two dampers affected by the
| | QCIR 87-048-12A, Instrument Calibration (SBGTS) performed July 22, The QC inspector witnessed calibration of 2 separate |
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| modification were wired incorrectly, a discrepancy between the modified dampers and non-modified dampers would have been apparent.
| | 1987 instrument loops being performed in accordance with an approved ) |
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| - | | procedure and also verified calibration status of all test equipment being use No deficiencies were noted by the QC inspecto QCIR 87-980, verification of correct installation of switch 42.1426-CS (SBGTS B train fan) performed August 2,1987. The QC inspector observed that the switch was installed in accordance with the PD ) |
| In either case, TP 87-128 specified the correct damper positions in Attachment E, Steps El thru E20. Therefore, if the discrepancies had not been previously identified, they would have been identified in these steps.
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| Procedure 1.3.4 "Procedures" defines the process by which procedures are revised when errors are identified. Prior to completion of the test, the discrepancy would have been resolved and TP 87-128 would have been corrected.
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| Section 2.2.8 states,
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| "Section 7.3.8 and 7.3.8.9 did not require verification that valve AON-112 closed when the 'B' Standby Gas Treatment System (SBGTS) fan tripped (per procedure). Inlet valve A0N-106 was verified as closing."
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| Response:
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| A0N-112 was verified to close during previous steps in the procedure which tested major portions of the circuit. Steps 7.3.8 and 7.3.8.9 tested discrete portions of the circuit that feed the previously tested A0N-112 circuit. Those portions of the circuit were verified to be functional by these steps. This overlapping test method adequately demonstrates functionality of the subject valve.
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| Section 2.2.C states,
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| "Paragraph 7.3.8.6 required the differential pressure across the calibrated perforated plate (DPI-AA-32) in the 'B' SBGTS train to be recorded with the 'B' SBGTS in standby (off). This reading was being taken to measure 'B' train bypass flow so it could be combined with 'A' train to determine system flow.
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| Under the system conditions specified this reading would be zero (0) since one of the SBGTS modifications moved the upstream i bypass flow connection such that the connection between the A l and B SBGTS trains is now downstream (bypassing) of the l calibrated orifice plate. The flow recorded on the 'A' i calibrated orifice plate would represent full system flow for the specified lineup." J l
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| Response: j Recording flow through the standby train of the SBGTS was recognized as not being required in the draft review of the procedure. It was determined that the reading should be left in the procedure based on the following:
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| Analysis of the data can be used to show no flow through the standby train when there should be no flow. This would reflect the integrity of the standby train inlet damper.
| | QCIR 87-14, Surveillance of the drilling of anchor bolt holes for hangers on the 41 foot 6 inch elevation of the reactor building, performed on January 6, 198 No discrepancies were observed by the QC inspecto QCIR's 87-75 and 87-81 concerned the witnessing of cables being pulled into the cable spreading room and into the control roo They were performed on January 27 and 28, 1987. No discrepancies were observed by the QC inspecto .3 Findings No violations were identified in the above revie .0 Independent Verification During the review discussed in Paragraph 2.2 the inspector independently calculated the various voltages required to give the desired vibration readings during the recirculation pump vibration monitor calibration check in TP 86-95. The inspectors calculations agreed with those contained in the procedur .0 Plant Tours The inspector toured various areas of the facility to assess plant and equipment conditions including cleanliness, fire hazards and work in progres No unacceptable conditions were observe .0 Exit Interview At the conclusion of the site inspection, on August 7, 1987, an exit interview was conducted with the licensee's senior site representatives (denoted iri Section 1). The findings were identified and inspection items were discusse _____- __ - |
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| ATTACHMENT (Cont.)
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| Reading standby train flow is of no consequence to the test performance or results.
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| Section 2.2.0 states,
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| "Train 'B' logic requires AON-106 damper (inlet) to open and pick up a position limit switch which allows the 'B' SBGTS fan to start and outlet damper A0N-112 to open. This logic sequence would occur during any start of the 'B' SBGTS train and was not checked in TP 87-128."
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| Response:
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| Although the logic sequence was not verified, the component functions were verified to occur. The actuation logic for this series of functions is as follows. A0N-106 opens which operates a limit switch starting the fan. A contact on the fan motor starter relay causes AON-il2 to open. This sequence was modified by the design. However, numerous independent wiring errors in several locations would be required for the components to function in other than the desired sequence. Design verification and construction verification, including QC verification of the as-built versus design configuration, provided assurance that the system wiring was correct.
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| Verification of the logic sequence was considered redundant.
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| Section 2.2.E states,
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| "The procedure did not verify that per design the 'B' S8GTS train would remain running after 20 minutes if the 'A' train had insufficient flow or was tripped with the 'B' train in standby.
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| The system is designed to trip the 'B' train after 20 minutes if sufficient flow exists."
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| Response: .
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| The design sequence of operation following auto initiation of the SBGTS is as follows:
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| Both 'A' and 'B' SBGTS trains start.
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| !
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| After 20 minutes of operation the standby ('B') train shutsdown, i
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| !
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| If insufficient flow or no flow (' A' SBGT fan tripped) is !
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| sensed, the standby ('B') train reinitiates after a 10 l second time delay and locks in for a continuous run. !
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| Section 7.3 of TP 87-128 properly demonstrated these functions.
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| This was discussed in detail with the inspector subsequent to the inspection. l Issue 3 - Review Requirements: '
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| 10CFR50 Appendix B. Criterion VI and BEQAM Section 6, require that i document control measures be established to control issue and i revision of documents which prescribe activities affecting quality. l These measures assure that documents, including changes, are reviewed for adequacy and approved for release by authorized personnel.
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| Page 4 of 5 I
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| ATTACHMENT (Cont.) ;
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| Both PDC 86-70 and TP 87-128 were reviewed and approved in accordance with approved BECO procedures. These procedures require multiple
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| , reviews and approvals that were fully documented in TP 87-128 and PDC 86-70. Based upon our response contained herein, we.believe that adequate reviews of both FCC 86-70 and TP B7-128 were performed.
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| Additional Actions: ,
| | At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensae representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction x l |
| The following additional actions have been taken or are planned to further strengthen the PDC process:
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| As immediate action the Nuclear Engineering Department issued Technical Quality Memo No. 92 on August 19, 1987, to reemphasize to engineering personnel the responsibility to clearly specify testing and acceptance requirements, in Plant Design Change packages. As committed in memo No. 92 NED procedures applicable to design verification testing will be revised to-clarify existing requirements.
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| Temporary Procedure (TP) 87-128 has been revised to correct the identified discrepancies. TP 87-128 Revision 3 was completed on
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| i August 29, 1987.
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| The Modifications Management Group of the Nuclear Operations Department has established a three man team to conduct independent reviews of the preoperational tests for the duration of RF0-7. This team provides additional assurance that the large number of modifications implemented during RF0 No. 7 receive a thorough review for preoperational testing requirements.
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Category:INSPECTION REPORT
MONTHYEARIR 05000293/19990051999-10-0808 October 1999 Insp Rept 50-293/99-05 on 990726-0905.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19990041999-08-27027 August 1999 Insp Rept 50-293/99-04 on 990610-0725.Non-cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20209G2331999-07-0909 July 1999 Insp Rept 50-293/99-03 on 990419-0609.Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support.Response to Main Transformer Fire by Fire Brigade Members Was Good IR 05000293/19990021999-05-17017 May 1999 Insp Rept 50-293/99-02 on 990308-0418.Two Level 4 Violations Occurred & Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000293/19990011999-04-20020 April 1999 Insp Rept 50-293/99-01 on 990125-0307.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Also Included Routine Core Insp of Security Program During Period of 990301-05 IR 05000293/19980101998-12-22022 December 1998 Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support,Including Implementation of Fire Protection Program IR 05000293/19980081998-12-0101 December 1998 Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19982031998-11-24024 November 1998 Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted. Major Areas Inspected:Capability of Selected Sys to Perform Safety Functions Required by Design Bases,Adherence of Sys to Design & Licensing Bases & Consistency of Configuration IR 05000293/19980071998-10-0707 October 1998 Insp Rept 50-293/98-07 on 980726-0906.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19980061998-08-28028 August 1998 Insp Rept 50-293/98-06 on 980609-0725.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19980091998-08-20020 August 1998 Insp Rept 50-293/98-09 on 980713-24.No Violations Noted. Major Areas Inspected:Engineering Activities in Areas Including Evaluations to Address Operability Concerns,C/A Process & Actions Associated W/Findings from Previous Insps IR 05000293/19980051998-07-0909 July 1998 Insp Rept 50-293/98-05 on 980421-0608.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Concerns W/Fire Proctection Area Were Identified ML20217P7801998-04-0303 April 1998 Insp Rept 50-293/98-03 on 980302-05 & 11-12.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Licensee Security Force Capability IR 05000293/19980011998-03-24024 March 1998 Insp Rept 50-293/98-01 on 980107-0224.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19970131998-02-0606 February 1998 Insp Rept 50-293/97-13 on 971111-980106.Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19970121997-12-17017 December 1997 Insp Rept 50-293/97-12 on 971006-10 & 1119.Violations Noted. Major Areas Inspected:Eq Documents for EQ Equipment That Required Requalification Due to Containment Environ Changes Resulting from CS Flow Rate Reduction in 1988 IR 05000293/19970111997-12-11011 December 1997 Insp Rept 50-293/97-11 on 970914-1110.Violations Noted:Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970101997-11-26026 November 1997 Insp Rept 50-293/97-10 on 971104-07.No Violations Noted. Major Areas Inspected:Emergency Response Organization, Simulated Events,Mitigation Actions Emergency Declarations & off-site Agencies IR 05000293/19970081997-10-24024 October 1997 Insp Rept 50-293/97-08 on 970805-0913.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support ML20198L9231997-10-21021 October 1997 Insp Rept 50-293/97-05 on 970514-0828.Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Engineering IR 05000293/19970071997-09-15015 September 1997 Insp Rept 50-293/97-07 on 970625-0816.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970801997-09-12012 September 1997 Insp Rept 50-293/97-80 on 970721-0801.Violations Noted.Major Areas Inspected:Effectiveness of Processes for Identifying Resolving & Preventing Issues That Degrade Quality of Plant Operations & Safety ML20216G8181997-09-0404 September 1997 Insp Rept 50-293/97-09 on 970827-28.No Violations Noted. Major Areas Inspected:Licensee Access Authorization Program IR 05000293/19970041997-08-0707 August 1997 Insp Rept 50-293/97-04 on 970505-23.No Violations Noted. Major Areas Inspected:Effectiveness of Licensees Efforts in Maintaining Design Basis of safety-related Sys ML20149K0431997-07-22022 July 1997 Insp Rept 50-293/97-03 on 970429-0624.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20141K7861997-05-22022 May 1997 Insp Rept 50-293/97-02 on 970303-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137E5671997-03-18018 March 1997 Insp Rept 50-293/97-01 on 970112-0302.Violations Noted.Major Areas Inspected:Operations,Engineering & Plant Support ML20134K5951997-02-0707 February 1997 Insp Rept 50-293/96-10 on 961123-970111.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19960081996-12-18018 December 1996 Insp Rept 50-293/96-08 on 960924-1122.Violation Noted.Major Areas Inspected:Engineering,Maint,Plant Support,Radioactive Effluent Controls Program,Radiological Environmental Monitoring & Meteorological Monitoring.Meeting Slides Encl IR 05000293/19960061996-10-30030 October 1996 Insp Rept 50-293/96-06 on 960729-0923.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129A0441996-10-11011 October 1996 Insp Rept 50-293/96-09 on 960916-20.Violations Noted. Major Areas Inspected:Miscellaneous Security & Safeguard Issues,Access Authorization Program & Administration Organization & Background Investigation Elements ML20129D8361996-09-20020 September 1996 Insp Rept 50-293/96-07 on 960708-12,0722-26 & 0828-0903. Non Cited Violation Noted.Major Areas Inspected:C/As After Licensee Had Identified Potentially Inoperable Primary Containment as Documented in LER 96-04 IR 05000293/19930201994-01-10010 January 1994 Insp Rept 50-293/93-20 on Stated Date.No Violations Noted. Major Areas Inspected:Operations,Maintenance & Surveillance, Engineering & Plant Support IR 05000293/19930801993-12-21021 December 1993 Insp Rept 50-293/93-80 on 931018-23.No Violations Noted. Major Areas Inspected:Station Blackout Coping Sys,Onsite Ac Supplies & Reliability Program,Plant Mods & QA & Maint Practices for Station Blackout Equipment IR 05000293/19930191993-11-23023 November 1993 Insp Rept 50-293/93-19 on 930928-1101.No Violations Noted. Major Areas Inspected:Plant Operations,Maint & Surveillance, Engineering,Plant Support,W/Regard to Security & NRC Info Notice 93-079 ML20058D4771993-11-19019 November 1993 Insp Rept 50-293/93-16 on 930830-1015.Violations Noted.Major Areas Inspected:Audits & Surveillances,Training & Qualifications,Radiological Problem Repts & Associated C/A IR 05000293/19930151993-10-15015 October 1993 Insp Rept 50-293/93-15 on 930817-0927.No Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls Maint & Surveillance,Emergency Preparedness,Security,Safety Assessment & Quality Verification IR 05000293/19930171993-09-24024 September 1993 Insp Rept 50-293/93-17 on 930830-0903.No Violations Noted. Major Areas Inspected:Mgt Controls,Qa Audits & ODCM IR 05000293/19930141993-09-0808 September 1993 Insp Rept 50-293/93-14 on 930713-0816.No Violations Noted. Major Areas Inspected:Plant Operations,Maintenance & Surveillance,Engineering & Plant Support IR 05000293/19930111993-08-0404 August 1993 Insp Rept 50-293/93-11 on 930606-11.No Violations Noted. Major Areas Inspected:Licensee Corrective Actions of Previously Identified Electrical Distribution Sys Functional Insp Findings & Observations IR 05000293/19930011993-02-0303 February 1993 Insp Rept 50-293/93-01 on 930111-14.Weaknesses Noted.Major Areas Inspected:Eop Review,Rev,Approval Process,Qa Involvement in EOP Program & Operator Training in EOPs IR 05000293/19920811993-02-0202 February 1993 Probabilistic Risk Assessment Based Insp Rept 50-293/92-81 on 921130-1218.Violation Noted.Major Areas Inspected:Review of Emergency Diesel Generators & Hpcis.App a Encl IR 05000293/19920281993-01-28028 January 1993 Insp Rept 50-293/92-28 on 921124-1231.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security,Safety Assessment & Quality Verification IR 05000293/19920261993-01-21021 January 1993 Insp Rept 50-293/92-26 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Ep Program Changes, Emergency Response Facilities,Equipment,Instrumentation, Supplies & Organization & Mgt Control IR 05000293/19920231992-12-29029 December 1992 Safety Insp Rept 50-293/92-23 on 921020-1123.No Violations Noted.Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security & Safety Assessment & Quality Verification IR 05000293/19920241992-11-23023 November 1992 Insp Rept 50-293/92-24 on Stated Date.No Safety Concerns or Violations Noted.Major Areas Inspected:Audits & Surveillances,Collective Personnel Exposure Status,Outage Radiological Controls & Implementation of Exposure Programs IR 05000293/19900201990-11-0707 November 1990 Safety Insp Rept 50-293/90-20 on 900816-1008.Violation Noted.Major Areas Inspected:Plant Operations,Security, Maint & Surveillance,Engineering & Technical Support, Radiological Controls,Emergency Preparedness & Safety IR 05000293/19900211990-10-11011 October 1990 Insp Rept 50-293/90-21 on 900905-07.Major Areas Inspected: 900902-03 Event Involving Number of Component Malfunctions & Operational Complications Following Shutdown.Operating Procedures Lacked Adequate Guidance for Operators IR 05000293/19900091990-08-20020 August 1990 Insp Rept 50-293/90-09 on 900806-10.No Violations or Deviations Noted.Major Areas Inspected:Control of Design, Design Changes,Mods,Engineering & Technical Support Organization,Staffing,Communications,Qa & Training IR 05000293/19900161990-07-30030 July 1990 Partially Withheld Physical Security Insp Rept 50-293/90-16 on 900625-29 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Mgt Support & Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids 1999-08-27
[Table view] Category:NRC-GENERATED
MONTHYEARIR 05000293/19990051999-10-0808 October 1999 Insp Rept 50-293/99-05 on 990726-0905.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19990041999-08-27027 August 1999 Insp Rept 50-293/99-04 on 990610-0725.Non-cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20209G2331999-07-0909 July 1999 Insp Rept 50-293/99-03 on 990419-0609.Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support.Response to Main Transformer Fire by Fire Brigade Members Was Good IR 05000293/19990021999-05-17017 May 1999 Insp Rept 50-293/99-02 on 990308-0418.Two Level 4 Violations Occurred & Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000293/19990011999-04-20020 April 1999 Insp Rept 50-293/99-01 on 990125-0307.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Also Included Routine Core Insp of Security Program During Period of 990301-05 IR 05000293/19980101998-12-22022 December 1998 Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support,Including Implementation of Fire Protection Program IR 05000293/19980081998-12-0101 December 1998 Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19982031998-11-24024 November 1998 Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted. Major Areas Inspected:Capability of Selected Sys to Perform Safety Functions Required by Design Bases,Adherence of Sys to Design & Licensing Bases & Consistency of Configuration IR 05000293/19980071998-10-0707 October 1998 Insp Rept 50-293/98-07 on 980726-0906.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19980061998-08-28028 August 1998 Insp Rept 50-293/98-06 on 980609-0725.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19980091998-08-20020 August 1998 Insp Rept 50-293/98-09 on 980713-24.No Violations Noted. Major Areas Inspected:Engineering Activities in Areas Including Evaluations to Address Operability Concerns,C/A Process & Actions Associated W/Findings from Previous Insps IR 05000293/19980051998-07-0909 July 1998 Insp Rept 50-293/98-05 on 980421-0608.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Concerns W/Fire Proctection Area Were Identified ML20217P7801998-04-0303 April 1998 Insp Rept 50-293/98-03 on 980302-05 & 11-12.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Licensee Security Force Capability IR 05000293/19980011998-03-24024 March 1998 Insp Rept 50-293/98-01 on 980107-0224.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19970131998-02-0606 February 1998 Insp Rept 50-293/97-13 on 971111-980106.Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19970121997-12-17017 December 1997 Insp Rept 50-293/97-12 on 971006-10 & 1119.Violations Noted. Major Areas Inspected:Eq Documents for EQ Equipment That Required Requalification Due to Containment Environ Changes Resulting from CS Flow Rate Reduction in 1988 IR 05000293/19970111997-12-11011 December 1997 Insp Rept 50-293/97-11 on 970914-1110.Violations Noted:Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970101997-11-26026 November 1997 Insp Rept 50-293/97-10 on 971104-07.No Violations Noted. Major Areas Inspected:Emergency Response Organization, Simulated Events,Mitigation Actions Emergency Declarations & off-site Agencies IR 05000293/19970081997-10-24024 October 1997 Insp Rept 50-293/97-08 on 970805-0913.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support ML20198L9231997-10-21021 October 1997 Insp Rept 50-293/97-05 on 970514-0828.Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Engineering IR 05000293/19970071997-09-15015 September 1997 Insp Rept 50-293/97-07 on 970625-0816.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970801997-09-12012 September 1997 Insp Rept 50-293/97-80 on 970721-0801.Violations Noted.Major Areas Inspected:Effectiveness of Processes for Identifying Resolving & Preventing Issues That Degrade Quality of Plant Operations & Safety ML20216G8181997-09-0404 September 1997 Insp Rept 50-293/97-09 on 970827-28.No Violations Noted. Major Areas Inspected:Licensee Access Authorization Program IR 05000293/19970041997-08-0707 August 1997 Insp Rept 50-293/97-04 on 970505-23.No Violations Noted. Major Areas Inspected:Effectiveness of Licensees Efforts in Maintaining Design Basis of safety-related Sys ML20149K0431997-07-22022 July 1997 Insp Rept 50-293/97-03 on 970429-0624.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20141K7861997-05-22022 May 1997 Insp Rept 50-293/97-02 on 970303-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137E5671997-03-18018 March 1997 Insp Rept 50-293/97-01 on 970112-0302.Violations Noted.Major Areas Inspected:Operations,Engineering & Plant Support ML20134K5951997-02-0707 February 1997 Insp Rept 50-293/96-10 on 961123-970111.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19960081996-12-18018 December 1996 Insp Rept 50-293/96-08 on 960924-1122.Violation Noted.Major Areas Inspected:Engineering,Maint,Plant Support,Radioactive Effluent Controls Program,Radiological Environmental Monitoring & Meteorological Monitoring.Meeting Slides Encl IR 05000293/19960061996-10-30030 October 1996 Insp Rept 50-293/96-06 on 960729-0923.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129A0441996-10-11011 October 1996 Insp Rept 50-293/96-09 on 960916-20.Violations Noted. Major Areas Inspected:Miscellaneous Security & Safeguard Issues,Access Authorization Program & Administration Organization & Background Investigation Elements ML20129D8361996-09-20020 September 1996 Insp Rept 50-293/96-07 on 960708-12,0722-26 & 0828-0903. Non Cited Violation Noted.Major Areas Inspected:C/As After Licensee Had Identified Potentially Inoperable Primary Containment as Documented in LER 96-04 IR 05000293/19930201994-01-10010 January 1994 Insp Rept 50-293/93-20 on Stated Date.No Violations Noted. Major Areas Inspected:Operations,Maintenance & Surveillance, Engineering & Plant Support IR 05000293/19930801993-12-21021 December 1993 Insp Rept 50-293/93-80 on 931018-23.No Violations Noted. Major Areas Inspected:Station Blackout Coping Sys,Onsite Ac Supplies & Reliability Program,Plant Mods & QA & Maint Practices for Station Blackout Equipment IR 05000293/19930191993-11-23023 November 1993 Insp Rept 50-293/93-19 on 930928-1101.No Violations Noted. Major Areas Inspected:Plant Operations,Maint & Surveillance, Engineering,Plant Support,W/Regard to Security & NRC Info Notice 93-079 ML20058D4771993-11-19019 November 1993 Insp Rept 50-293/93-16 on 930830-1015.Violations Noted.Major Areas Inspected:Audits & Surveillances,Training & Qualifications,Radiological Problem Repts & Associated C/A IR 05000293/19930151993-10-15015 October 1993 Insp Rept 50-293/93-15 on 930817-0927.No Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls Maint & Surveillance,Emergency Preparedness,Security,Safety Assessment & Quality Verification IR 05000293/19930171993-09-24024 September 1993 Insp Rept 50-293/93-17 on 930830-0903.No Violations Noted. Major Areas Inspected:Mgt Controls,Qa Audits & ODCM IR 05000293/19930141993-09-0808 September 1993 Insp Rept 50-293/93-14 on 930713-0816.No Violations Noted. Major Areas Inspected:Plant Operations,Maintenance & Surveillance,Engineering & Plant Support IR 05000293/19930111993-08-0404 August 1993 Insp Rept 50-293/93-11 on 930606-11.No Violations Noted. Major Areas Inspected:Licensee Corrective Actions of Previously Identified Electrical Distribution Sys Functional Insp Findings & Observations IR 05000293/19930011993-02-0303 February 1993 Insp Rept 50-293/93-01 on 930111-14.Weaknesses Noted.Major Areas Inspected:Eop Review,Rev,Approval Process,Qa Involvement in EOP Program & Operator Training in EOPs IR 05000293/19920811993-02-0202 February 1993 Probabilistic Risk Assessment Based Insp Rept 50-293/92-81 on 921130-1218.Violation Noted.Major Areas Inspected:Review of Emergency Diesel Generators & Hpcis.App a Encl IR 05000293/19920281993-01-28028 January 1993 Insp Rept 50-293/92-28 on 921124-1231.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security,Safety Assessment & Quality Verification IR 05000293/19920261993-01-21021 January 1993 Insp Rept 50-293/92-26 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Ep Program Changes, Emergency Response Facilities,Equipment,Instrumentation, Supplies & Organization & Mgt Control IR 05000293/19920231992-12-29029 December 1992 Safety Insp Rept 50-293/92-23 on 921020-1123.No Violations Noted.Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security & Safety Assessment & Quality Verification IR 05000293/19920241992-11-23023 November 1992 Insp Rept 50-293/92-24 on Stated Date.No Safety Concerns or Violations Noted.Major Areas Inspected:Audits & Surveillances,Collective Personnel Exposure Status,Outage Radiological Controls & Implementation of Exposure Programs IR 05000293/19900201990-11-0707 November 1990 Safety Insp Rept 50-293/90-20 on 900816-1008.Violation Noted.Major Areas Inspected:Plant Operations,Security, Maint & Surveillance,Engineering & Technical Support, Radiological Controls,Emergency Preparedness & Safety IR 05000293/19900211990-10-11011 October 1990 Insp Rept 50-293/90-21 on 900905-07.Major Areas Inspected: 900902-03 Event Involving Number of Component Malfunctions & Operational Complications Following Shutdown.Operating Procedures Lacked Adequate Guidance for Operators IR 05000293/19900091990-08-20020 August 1990 Insp Rept 50-293/90-09 on 900806-10.No Violations or Deviations Noted.Major Areas Inspected:Control of Design, Design Changes,Mods,Engineering & Technical Support Organization,Staffing,Communications,Qa & Training IR 05000293/19900161990-07-30030 July 1990 Partially Withheld Physical Security Insp Rept 50-293/90-16 on 900625-29 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Mgt Support & Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids 1999-08-27
[Table view] Category:INSPECTION REPORT
MONTHYEARIR 05000293/19990051999-10-0808 October 1999 Insp Rept 50-293/99-05 on 990726-0905.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19990041999-08-27027 August 1999 Insp Rept 50-293/99-04 on 990610-0725.Non-cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20209G2331999-07-0909 July 1999 Insp Rept 50-293/99-03 on 990419-0609.Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support.Response to Main Transformer Fire by Fire Brigade Members Was Good IR 05000293/19990021999-05-17017 May 1999 Insp Rept 50-293/99-02 on 990308-0418.Two Level 4 Violations Occurred & Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000293/19990011999-04-20020 April 1999 Insp Rept 50-293/99-01 on 990125-0307.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Also Included Routine Core Insp of Security Program During Period of 990301-05 IR 05000293/19980101998-12-22022 December 1998 Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support,Including Implementation of Fire Protection Program IR 05000293/19980081998-12-0101 December 1998 Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19982031998-11-24024 November 1998 Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted. Major Areas Inspected:Capability of Selected Sys to Perform Safety Functions Required by Design Bases,Adherence of Sys to Design & Licensing Bases & Consistency of Configuration IR 05000293/19980071998-10-0707 October 1998 Insp Rept 50-293/98-07 on 980726-0906.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19980061998-08-28028 August 1998 Insp Rept 50-293/98-06 on 980609-0725.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19980091998-08-20020 August 1998 Insp Rept 50-293/98-09 on 980713-24.No Violations Noted. Major Areas Inspected:Engineering Activities in Areas Including Evaluations to Address Operability Concerns,C/A Process & Actions Associated W/Findings from Previous Insps IR 05000293/19980051998-07-0909 July 1998 Insp Rept 50-293/98-05 on 980421-0608.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Concerns W/Fire Proctection Area Were Identified ML20217P7801998-04-0303 April 1998 Insp Rept 50-293/98-03 on 980302-05 & 11-12.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Licensee Security Force Capability IR 05000293/19980011998-03-24024 March 1998 Insp Rept 50-293/98-01 on 980107-0224.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19970131998-02-0606 February 1998 Insp Rept 50-293/97-13 on 971111-980106.Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19970121997-12-17017 December 1997 Insp Rept 50-293/97-12 on 971006-10 & 1119.Violations Noted. Major Areas Inspected:Eq Documents for EQ Equipment That Required Requalification Due to Containment Environ Changes Resulting from CS Flow Rate Reduction in 1988 IR 05000293/19970111997-12-11011 December 1997 Insp Rept 50-293/97-11 on 970914-1110.Violations Noted:Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970101997-11-26026 November 1997 Insp Rept 50-293/97-10 on 971104-07.No Violations Noted. Major Areas Inspected:Emergency Response Organization, Simulated Events,Mitigation Actions Emergency Declarations & off-site Agencies IR 05000293/19970081997-10-24024 October 1997 Insp Rept 50-293/97-08 on 970805-0913.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support ML20198L9231997-10-21021 October 1997 Insp Rept 50-293/97-05 on 970514-0828.Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Engineering IR 05000293/19970071997-09-15015 September 1997 Insp Rept 50-293/97-07 on 970625-0816.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970801997-09-12012 September 1997 Insp Rept 50-293/97-80 on 970721-0801.Violations Noted.Major Areas Inspected:Effectiveness of Processes for Identifying Resolving & Preventing Issues That Degrade Quality of Plant Operations & Safety ML20216G8181997-09-0404 September 1997 Insp Rept 50-293/97-09 on 970827-28.No Violations Noted. Major Areas Inspected:Licensee Access Authorization Program IR 05000293/19970041997-08-0707 August 1997 Insp Rept 50-293/97-04 on 970505-23.No Violations Noted. Major Areas Inspected:Effectiveness of Licensees Efforts in Maintaining Design Basis of safety-related Sys ML20149K0431997-07-22022 July 1997 Insp Rept 50-293/97-03 on 970429-0624.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20141K7861997-05-22022 May 1997 Insp Rept 50-293/97-02 on 970303-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20137E5671997-03-18018 March 1997 Insp Rept 50-293/97-01 on 970112-0302.Violations Noted.Major Areas Inspected:Operations,Engineering & Plant Support ML20134K5951997-02-0707 February 1997 Insp Rept 50-293/96-10 on 961123-970111.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19960081996-12-18018 December 1996 Insp Rept 50-293/96-08 on 960924-1122.Violation Noted.Major Areas Inspected:Engineering,Maint,Plant Support,Radioactive Effluent Controls Program,Radiological Environmental Monitoring & Meteorological Monitoring.Meeting Slides Encl IR 05000293/19960061996-10-30030 October 1996 Insp Rept 50-293/96-06 on 960729-0923.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20129A0441996-10-11011 October 1996 Insp Rept 50-293/96-09 on 960916-20.Violations Noted. Major Areas Inspected:Miscellaneous Security & Safeguard Issues,Access Authorization Program & Administration Organization & Background Investigation Elements ML20129D8361996-09-20020 September 1996 Insp Rept 50-293/96-07 on 960708-12,0722-26 & 0828-0903. Non Cited Violation Noted.Major Areas Inspected:C/As After Licensee Had Identified Potentially Inoperable Primary Containment as Documented in LER 96-04 IR 05000293/19930201994-01-10010 January 1994 Insp Rept 50-293/93-20 on Stated Date.No Violations Noted. Major Areas Inspected:Operations,Maintenance & Surveillance, Engineering & Plant Support IR 05000293/19930801993-12-21021 December 1993 Insp Rept 50-293/93-80 on 931018-23.No Violations Noted. Major Areas Inspected:Station Blackout Coping Sys,Onsite Ac Supplies & Reliability Program,Plant Mods & QA & Maint Practices for Station Blackout Equipment IR 05000293/19930191993-11-23023 November 1993 Insp Rept 50-293/93-19 on 930928-1101.No Violations Noted. Major Areas Inspected:Plant Operations,Maint & Surveillance, Engineering,Plant Support,W/Regard to Security & NRC Info Notice 93-079 ML20058D4771993-11-19019 November 1993 Insp Rept 50-293/93-16 on 930830-1015.Violations Noted.Major Areas Inspected:Audits & Surveillances,Training & Qualifications,Radiological Problem Repts & Associated C/A IR 05000293/19930151993-10-15015 October 1993 Insp Rept 50-293/93-15 on 930817-0927.No Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls Maint & Surveillance,Emergency Preparedness,Security,Safety Assessment & Quality Verification IR 05000293/19930171993-09-24024 September 1993 Insp Rept 50-293/93-17 on 930830-0903.No Violations Noted. Major Areas Inspected:Mgt Controls,Qa Audits & ODCM IR 05000293/19930141993-09-0808 September 1993 Insp Rept 50-293/93-14 on 930713-0816.No Violations Noted. Major Areas Inspected:Plant Operations,Maintenance & Surveillance,Engineering & Plant Support IR 05000293/19930111993-08-0404 August 1993 Insp Rept 50-293/93-11 on 930606-11.No Violations Noted. Major Areas Inspected:Licensee Corrective Actions of Previously Identified Electrical Distribution Sys Functional Insp Findings & Observations IR 05000293/19930011993-02-0303 February 1993 Insp Rept 50-293/93-01 on 930111-14.Weaknesses Noted.Major Areas Inspected:Eop Review,Rev,Approval Process,Qa Involvement in EOP Program & Operator Training in EOPs IR 05000293/19920811993-02-0202 February 1993 Probabilistic Risk Assessment Based Insp Rept 50-293/92-81 on 921130-1218.Violation Noted.Major Areas Inspected:Review of Emergency Diesel Generators & Hpcis.App a Encl IR 05000293/19920281993-01-28028 January 1993 Insp Rept 50-293/92-28 on 921124-1231.Violations Noted. Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security,Safety Assessment & Quality Verification IR 05000293/19920261993-01-21021 January 1993 Insp Rept 50-293/92-26 on 921207-11.No Violations or Deviations Noted.Major Areas Inspected:Ep Program Changes, Emergency Response Facilities,Equipment,Instrumentation, Supplies & Organization & Mgt Control IR 05000293/19920231992-12-29029 December 1992 Safety Insp Rept 50-293/92-23 on 921020-1123.No Violations Noted.Major Areas Inspected:Plant Operations,Radiological Controls,Maint & Surveillance,Emergency Preparedness, Security & Safety Assessment & Quality Verification IR 05000293/19920241992-11-23023 November 1992 Insp Rept 50-293/92-24 on Stated Date.No Safety Concerns or Violations Noted.Major Areas Inspected:Audits & Surveillances,Collective Personnel Exposure Status,Outage Radiological Controls & Implementation of Exposure Programs IR 05000293/19900201990-11-0707 November 1990 Safety Insp Rept 50-293/90-20 on 900816-1008.Violation Noted.Major Areas Inspected:Plant Operations,Security, Maint & Surveillance,Engineering & Technical Support, Radiological Controls,Emergency Preparedness & Safety IR 05000293/19900211990-10-11011 October 1990 Insp Rept 50-293/90-21 on 900905-07.Major Areas Inspected: 900902-03 Event Involving Number of Component Malfunctions & Operational Complications Following Shutdown.Operating Procedures Lacked Adequate Guidance for Operators IR 05000293/19900091990-08-20020 August 1990 Insp Rept 50-293/90-09 on 900806-10.No Violations or Deviations Noted.Major Areas Inspected:Control of Design, Design Changes,Mods,Engineering & Technical Support Organization,Staffing,Communications,Qa & Training IR 05000293/19900161990-07-30030 July 1990 Partially Withheld Physical Security Insp Rept 50-293/90-16 on 900625-29 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Mgt Support & Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids 1999-08-27
[Table view] Category:UTILITY
MONTHYEARIR 05000293/19900201990-11-0707 November 1990 Safety Insp Rept 50-293/90-20 on 900816-1008.Violation Noted.Major Areas Inspected:Plant Operations,Security, Maint & Surveillance,Engineering & Technical Support, Radiological Controls,Emergency Preparedness & Safety IR 05000293/19900211990-10-11011 October 1990 Insp Rept 50-293/90-21 on 900905-07.Major Areas Inspected: 900902-03 Event Involving Number of Component Malfunctions & Operational Complications Following Shutdown.Operating Procedures Lacked Adequate Guidance for Operators IR 05000293/19900091990-08-20020 August 1990 Insp Rept 50-293/90-09 on 900806-10.No Violations or Deviations Noted.Major Areas Inspected:Control of Design, Design Changes,Mods,Engineering & Technical Support Organization,Staffing,Communications,Qa & Training IR 05000293/19900161990-07-30030 July 1990 Partially Withheld Physical Security Insp Rept 50-293/90-16 on 900625-29 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Mgt Support & Program Plans,Protected & Vital Area Physical Barriers & Detection & Assessment Aids IR 05000293/19900181990-07-26026 July 1990 Insp Rept 50-293/90-18 on 900709-13.No Violations Noted. Major Areas Inspected:Inservice Insp Activities to Ascertain Whether Licensee Activities Conducted in Compliance W/Asme Code & Regulatory Requirements IR 05000293/19900171990-07-25025 July 1990 Insp Rept 50-293/90-17 on 900624-29.No Violations Noted. Major Areas Inspected:Radiological & Nonradiological Chemistry Programs IR 05000293/19900131990-06-29029 June 1990 Safety Insp Rept 50-293/90-13 on 900501-0611.No Violations Noted.Major Areas Inspected:Actions on Previous Insp Findings,Plant Operations,Security,Maint & Surveillance, Engineering Support & Radiological Controls IR 05000293/19900141990-06-26026 June 1990 Insp Rept 50-293/90-14 on 900620-22.No Violations Noted. Major Areas Inspected:Observation of Licensee Partial Participation Annual Emergency Preparedness Exercise IR 05000293/19890061989-07-20020 July 1989 Insp Rept 50-293/89-06 on 890411-0524.No Violations Noted. Major Areas Inspected:Assessment of Licensee Mgt Controls, Conduct of Operation & Licensee Approach to Investigation & Resolution of Events During 5 - 25% Power Plateau IR 05000293/19890091989-07-0606 July 1989 Insp Rept 50-293/89-09 on 890619-22.No Violations Noted. Major Areas Inspected:Changes to Emergency Preparedness Program,Emergency Facilities,Equipment,Instrumentation & Supplies,Organization & Mgt Control IR 05000293/19890051989-06-0909 June 1989 Insp Rept 50-293/89-05 on 890311-0410.Unresolved Item Noted Re Util Method for Disabling Annunciators in Control Room. Major Areas Inspected:Assessment of Licensee Mgt Controls, Conduct of Operations & Startup Testing ML20247D5561989-05-0808 May 1989 Augmented Insp Team Rept 50-293/89-80 on 890413-15 & 17-26. No Violations Noted.Major Areas Inspected:Causes,Safety Implications & Util Response to 890412 RCIC Sys Suction Piping Overpressurization IR 05000293/19890041989-04-28028 April 1989 Mgt Meeting Rept 50-293/89-04 on 890328-30.Major Areas Discussed:Emergency Plan & Implementing Procedures, Emergency Operations Ctr Staffing & Equipment,Reception Ctrs & Public Info Brochure IR 05000293/19890011989-04-24024 April 1989 Insp Rept 50-293/89-01 on 890206-0310.Violations Noted.Major Areas Inspected:Licensee Mgt Controls,Conduct of Operations & Startup Testing Activities During Licensee Power Ascension Program IR 05000293/19890431989-04-0606 April 1989 Mgt Meeting Rept 50-293/89-43 on 890309 Re Licensee Followup to 890304 Reactor Scram & Util Overview of Turbine Control Sys IR 05000293/19880371989-03-30030 March 1989 Insp Rept 50-293/88-37 on 881227-890205.Violation Noted Re Failure to Control Locked High Radiation Area Access.Major Areas Inspected:Licensee Mgt Controls,Conduct of Operations & Startup Testing During Power Ascension Program IR 05000293/19890031989-02-21021 February 1989 Meeting Rept 50-293/89-03 on 890131-0202.Major Areas Discussed:Emergency Operating Conditions,Training,Staffing, Emergency Plan & Implementing Procedures & Equipment IR 05000293/19880341989-02-14014 February 1989 Safety Insp Rept 50-293/88-34 on 881114-1226.No Violations Noted.Major Areas Inspected:Plant Operations,Radiation Protection,Physical Security,Plant Events,Maint, Surveillance,Part 21 Repts & Outage Activities IR 05000293/19870991989-01-0606 January 1989 Mgt Meeting Rept on 881003 to Review Licensee Actions to Address Radiation Protection Program Weaknesses Described in SALP Rept 50-293/87-99 ML20206L4581988-11-21021 November 1988 Insp Rept 50-293/88-30 on 881027-1118.No Violations Noted. Major Areas Inspected:Licensee Followup Activities Re Loose Anchor Bolts in Pipe Support Base Plate,Safety Significance of Subj Discrepancy & Response to Bulletins 79-002 & 79-014 IR 05000293/19880311988-10-24024 October 1988 Insp Rept 50-293/88-31 on 880829-0926.Violations Noted.Major Areas Inspected:Radiation Protection,Physical Security, Plant Events,Maint,Surveillance & Outage Activities IR 05000293/19880321988-10-13013 October 1988 Insp Rept 50-293/88-32 on 880912-16.Violations Noted.Major Areas Inspected:Corrective Actions That Resulted from IE Bulletin 85-003 That Addressed Improper Limit Switch & Torque Switch Settings in motor-operated Valves IR 05000293/19880271988-09-20020 September 1988 Insp Rept 50-293/88-27 on 880718-0828.No Violations Noted. Major Areas Inspected:Licensee Actions on Previous Insp Findings,Plant Operations,Radiation Protection & Physical Security.One Unresolved Item Identified Re Valve Yoke Clamp ML20154C2791988-09-0707 September 1988 Integrated Assessment Team Insp Rept 50-293/88-21 on 880808- -24.No Violations Noted.Major Areas Inspected:Degree of Readiness of Licensee Mgt Controls,Programs & Personnel to Support Safe Restart & Plant Operation IR 05000283/19880291988-09-0707 September 1988 Insp Rept 50-283/88-29 on 880818-20.No Violations or Deviations Noted.Major Areas Inspected:Use of NRC Mobile Radioanalytical Lab to Perform Independent Measurements of Soil to Determine Existence & Level of Contamination ML20154L5851988-09-0606 September 1988 Meeting Rept 50-293/M88-312 on 880831.Discusses NRC Concerns Re Rosemount 1153 Transmitter Ringing Problem & Util Approach to Resolving Issue ML20153D3051988-08-23023 August 1988 Insp Rept 50-293/88-23 on 880620-30.No Violations Noted. Major Areas Inspected:Licensee Corrective Actions in Response to NRC Info Notices 86-003 & 053 Re Limitorque Valves & Raychem Heat Shrink Tubing,Respectively IR 05000293/19880251988-08-15015 August 1988 Insp Rept 50-293/88-25 on 880601-0717.No Violations Noted. Major Areas Inspected:Plant Operations,Radiation Protection, Physical Security,Plant Events,Maint,Surveillance,Outage Activities & Repts to NRC IR 05000293/19880281988-07-26026 July 1988 Insp Rept 50-293/88-28 on 880718-21.No Violations Noted. Major Areas Inspected:Changes to Emergency Preparedness Program,Shift Staffing & Augmentation,Knowledge & Performance of Duties & Emergency Detection IR 05000293/19880241988-07-22022 July 1988 Insp Rept 50-293/88-24 on 880531-0609.No Violations Noted. Major Areas Inspected:Licensee Followup & Corrective Actions Re Several Previously Identified Open Items IR 05000293/19880201988-07-18018 July 1988 Insp Rept 50-293/88-20 on 880502-0610.No Violations Noted. Major Areas Inspected:Qa Aspects of Mod Covering Matls, Welding & NDE IR 05000293/19880181988-07-11011 July 1988 Physical Security Insp Rept 50-293/88-18 on 880425-29 & 0503-04.No Violations Noted.Major Areas Inspected:Mgt Effectiveness of Licensee Proprietary Security Organization ML20150E8141988-06-30030 June 1988 Mgt Meeting Rept 50-293/88-26 on 880627.Major Issues Discussed:Licensee Response to NRC Maint Team Insp 50-293/88-17,status of Licensee Evaluation of RHR Valve Yoke Cracking & Followup of Assessment of Readiness for Restart IR 05000293/19880191988-06-28028 June 1988 Insp Rept 50-293/88-19 on 880418-0531.Concerns Noted.Major Areas Inspected:Plant Operations,Radiation Protection, Physical Security,Plant Events,Maint,Surveillance,Outage Activities & Repts to NRC IR 05000293/19880121988-05-31031 May 1988 Insp Rept 50-293/88-12 on 880306-0417.Violations Noted. Major Areas Inspected:Radiation Protection,Physical Security,Plant Events,Maint,Surveillance,Outage Activites & Repts to NRC IR 05000293/19880171988-05-25025 May 1988 Insp Rept 50-293/88-17 on 880425-0505.No Violations Noted. Major Areas Inspected:Exam of Identified Maint Problems, Correction of Problems & Maint Section Interfaces W/ Engineering,Operations,Qa & Health Physics Personnel ML20154F9341988-05-17017 May 1988 Insp Rept 50-293/88-11 on 880314-18.No Violations or Deviations Noted.Major Areas Inspected:Emergency Operating Procedures,Including Comparison of Plant Specific Guidelines & BWR Owners Group Guidelines with Emergency Procedures IR 05000293/19880141988-05-16016 May 1988 Insp Rept 50-293/88-14 on 880418-22.No Violations Noted. Major Areas Inspected:Previous Insp Findings & Power Ascension Test Program IR 05000293/19880161988-05-13013 May 1988 Partially Withheld Physical Security Insp Rept 50-293/88-16 on 880411-14 (Ref 10CFR73.21).No Violations Noted.Major Areas Inspected:Program Upgrades,Program Audits,Physical barriers-protected & Vital Areas & Lighting IR 05000293/19880131988-05-10010 May 1988 Insp Rept 50-293/88-13 on 880411-15.No Violations Noted. Major Areas Inspected:Review of Licensee Followup & Corrective Actions Re Previously Identified Open Items in Area of Matls Component Integrity & Plant Mods IR 05000293/19880431988-05-0909 May 1988 Mgt Meeting Rept 50-293/88-43 on 880408.Major Topic Discussed:Licensee Power Ascension Program.Viewgraphs Encl IR 05000293/19880071988-05-0606 May 1988 Insp Rept 50-293/88-07 on 880120-0305.Violations Noted.Major Areas Inspected:Insp of Plant Operations,Radiation Protection,Physical Security,Plant Events,Maint, Surveillance,Outage Activities & Repts to NRC IR 05000293/19880151988-04-27027 April 1988 Insp Rept 50-293/88-15 on 880404-08.No Violations Noted. Major Areas Inspected:Liquid Radwaste Sys,Solid Radwaste Sys & Gaseous Radwaste Sys IR 05000293/19880081988-04-19019 April 1988 Insp Rept 50-293/88-08 on 880201-05.Violations Noted.Major Areas Inspected:Electrical Power Sys,Including Verification of as-built Drawings,Adequacy of Breaker & Fuse Coordination & Emergency Loading of Diesel Generator IR 05000293/19880021988-04-14014 April 1988 Insp Rept 50-293/88-02 on 880125-0204.No Violations Noted. Major Areas Inspected:Matl Condition Improvement Action Program ML20151C5891988-03-31031 March 1988 Mgt Meeting Rept 50-293/87-30 on 870930.Major Areas Discussed:Followup of 870909 Enforcement Conference,Licensee Responses to Apparent Violations Identified in Insp Rept 50-293/87-30 & Programmatic Security Improvements IR 05000293/19880101988-03-14014 March 1988 Mgt Meeting Insp Rept 50-293/88-10 on 880224.Major Areas Discussed:Util Self Assessment Process Designed to Determine Readiness for Requesting Restart ML20153A8581988-03-11011 March 1988 Insp Rept 50-293/87-57 on 871207-880119.Violation Noted. Major Areas Inspected:Plant Operations,Radiation Protection, Physical Security,Plant Events,Maint & Surveillance.One Unresolved Item Identified IR 05000293/19880091988-03-10010 March 1988 Insp Rept 50-293/88-09 on 880124-25.No Violations Noted. Major Areas Inspected:Conditions Surrounding Classification & Reporting of Notification of Unusual Event Identified on 880211 IR 05000293/19880011988-03-0303 March 1988 Insp Rept 50-293/88-01 on 880125-29.No Violations Noted. Major Areas Inspected:Status of Previously Identified Items, Organization & Staffing,Control of Locked High Radiation Areas & Control of Hot Particles 1990-08-20
[Table view] Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARIR 05000293/19990051999-10-0808 October 1999 Insp Rept 50-293/99-05 on 990726-0905.Violations Noted.Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19990041999-08-27027 August 1999 Insp Rept 50-293/99-04 on 990610-0725.Non-cited Violations Noted.Major Areas Inspected:Aspects of Licensee Operations, Engineering,Maint & Plant Support ML20209G2331999-07-0909 July 1999 Insp Rept 50-293/99-03 on 990419-0609.Violations Noted & Being Treated as non-cited Violations.Major Areas Inspected: Operations,Maint,Engineering & Plant Support.Response to Main Transformer Fire by Fire Brigade Members Was Good PNO-I-99-026A, on 990518,main Transformer Was Damaged During Testing of Replacement Bushing While Unit Was in Refueling Outage.Current Refueling Outage Was Originally Scheduled to Be Completed on 990607,with Return to Full Power Operation1999-06-0101 June 1999 PNO-I-99-026A:on 990518,main Transformer Was Damaged During Testing of Replacement Bushing While Unit Was in Refueling Outage.Current Refueling Outage Was Originally Scheduled to Be Completed on 990607,with Return to Full Power Operation PNO-I-99-026, on 990518,fire Occurred at Pilgrim Station in Main Electrical Transformer.Licensee Requested off-site Firefighting Assistance.Resident Inspector Responded to Site Upon Notification of Event.Licensee Issued Press Release1999-05-19019 May 1999 PNO-I-99-026:on 990518,fire Occurred at Pilgrim Station in Main Electrical Transformer.Licensee Requested off-site Firefighting Assistance.Resident Inspector Responded to Site Upon Notification of Event.Licensee Issued Press Release IR 05000293/19990021999-05-17017 May 1999 Insp Rept 50-293/99-02 on 990308-0418.Two Level 4 Violations Occurred & Being Treated as Ncv.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000293/19990011999-04-20020 April 1999 Insp Rept 50-293/99-01 on 990125-0307.Violations Noted. Major Areas Inspected:Operations,Engineering,Maintenance & Plant Support.Also Included Routine Core Insp of Security Program During Period of 990301-05 IR 05000293/19980101998-12-22022 December 1998 Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support,Including Implementation of Fire Protection Program IR 05000293/19980081998-12-0101 December 1998 Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19982031998-11-24024 November 1998 Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted. Major Areas Inspected:Capability of Selected Sys to Perform Safety Functions Required by Design Bases,Adherence of Sys to Design & Licensing Bases & Consistency of Configuration IR 05000293/19983011998-11-24024 November 1998 NRC Operator Licensing Exam Rept 50-293/98-301OL (Including Completed & Graded Tests) for Tests Administered on 981016- 23.Exam Results:All Applicants Passed All Portions of Exam ML20154J8991998-10-0707 October 1998 Notice of Violation from Insp on 980726-0906.Violation Noted:Licensee Did Not Establish Measures to Assure Regulatory Requirements & Design Basis of Control Room High Efficiency Air Filtration Sys IR 05000293/19980071998-10-0707 October 1998 Insp Rept 50-293/98-07 on 980726-0906.Violations Noted.Major Areas Inspected:Operations,Maint,Engineering & Plant Support ML20239A1231998-08-28028 August 1998 Notice of Violation from Insp on 980609-0725.Violation Noted:From 1980 to 980609,licensee Failed to Maintain Provisions to Ensure That One Train of Cables Were Free from Fire Damage IR 05000293/19980061998-08-28028 August 1998 Insp Rept 50-293/98-06 on 980609-0725.No Violations Noted. Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support IR 05000293/19980091998-08-20020 August 1998 Insp Rept 50-293/98-09 on 980713-24.No Violations Noted. Major Areas Inspected:Engineering Activities in Areas Including Evaluations to Address Operability Concerns,C/A Process & Actions Associated W/Findings from Previous Insps ML20237A3031998-08-0606 August 1998 Notice of Violation from Insp on 980427-0515.Violation Noted:From 960710-970427,licensee Elected Not to Monitor Performance or Condition of Control Rod Drive Sys Against Established Goals IR 05000293/19980051998-07-0909 July 1998 Insp Rept 50-293/98-05 on 980421-0608.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support.Concerns W/Fire Proctection Area Were Identified ML20247N8441998-05-19019 May 1998 Partially Deleted Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000 (Ref 10CFR2.790(b) for Violations Noted During Insp on 980302-05 & 11-12 ML20247P0221998-05-19019 May 1998 Notice of Violation from Insp on 980225-0418.Violations Noted:Work Plan to Replace External Cooling Water Flexible Hoses to a Core Spray Pump Motor Not Commensurate with Complexity of Task.As Result,Physical Damage Occurred ML20248J3981998-05-14014 May 1998 EN-98-038:on 980519,notice of Proposed Imposition of Civil Penalty in Amount of $55,000 Issued to Licensee.Action Based on One Violation Involving Apparent Failures Associated W/Assessment Aids at Facility ML20217N5971998-04-27027 April 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $165,000.Violations Noted:Between Jan 1995 & 970120 Licensee Failed to Take Prompt & Effective Corrective Action for Significant Condition Adverse to Quality ML20247M3891998-04-22022 April 1998 EN-98-032:on 980427,notice of Proposed Imposition of Civil Penalty in Amount of $165,000 Issued to Licensee.Action Based on Two Severity Level III Violations & One Severity Level III Problem Re Failure to Identify & Take C/As ML20217P7801998-04-0303 April 1998 Insp Rept 50-293/98-03 on 980302-05 & 11-12.Apparent Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Licensee Security Force Capability ML20217F0101998-03-24024 March 1998 Notice of Violation from Insp on 980107-0224.Violation Noted:Nrc Identified That Condition Outside Design Basis of Plant Involving EDG Fuel Oil Storage Sys Was Not Reported to NRC within 1 Hour IR 05000293/19980011998-03-24024 March 1998 Insp Rept 50-293/98-01 on 980107-0224.Violations Noted.Major Areas Inspected:Licensee Operations,Engineering,Maint & Plant Support ML20202D2441998-02-0606 February 1998 Notice of Violation from Insp on 971111-980106.Violations Noted:Util Did Not Properly Evaluate Cause & Implement Corrective Actions to Preclude Repetition of Temporary Temp Detectors Deficiencies from Reactor Vessel Flange IR 05000293/19970131998-02-0606 February 1998 Insp Rept 50-293/97-13 on 971111-980106.Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support IR 05000293/19970121997-12-17017 December 1997 Insp Rept 50-293/97-12 on 971006-10 & 1119.Violations Noted. Major Areas Inspected:Eq Documents for EQ Equipment That Required Requalification Due to Containment Environ Changes Resulting from CS Flow Rate Reduction in 1988 ML20197K1101997-12-17017 December 1997 Notice of Violation from Insp on 971006-10 & 1119.Violation Noted:Nine Penetrations Were Not Qualified in That Qualification Methodology Used by Boston Edison Had Not Been Validated by Test Results to Be Equivalent to Type Testing ML20197H2411997-12-11011 December 1997 Notice of Violation from Insp on 970914-1110.Violation Noted:On 971001,licensee Identified That,Tagout T97-61-162 Was Incorrectly Prepared & Applied;Breaker 1021 Was Placed in Closed Vice Open Position as Required by Tagout IR 05000293/19970111997-12-11011 December 1997 Insp Rept 50-293/97-11 on 970914-1110.Violations Noted:Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970991997-11-26026 November 1997 Correction to SALP Rept 50-293/97-99.Page 2 of Subj Rept Corrected IR 05000293/19970101997-11-26026 November 1997 Insp Rept 50-293/97-10 on 971104-07.No Violations Noted. Major Areas Inspected:Emergency Response Organization, Simulated Events,Mitigation Actions Emergency Declarations & off-site Agencies PNO-I-97-072, on 971123,operators Initiated Plant Shutdown When Main Steam Isolation Valves AO-203-1C & AO-203-2B Were Declared Inoperable During Surveillance Test1997-11-24024 November 1997 PNO-I-97-072:on 971123,operators Initiated Plant Shutdown When Main Steam Isolation Valves AO-203-1C & AO-203-2B Were Declared Inoperable During Surveillance Test ML20198P8241997-11-0404 November 1997 SALP Rept 50-293/97-99 for Period 960407-970913 IR 05000293/19970081997-10-24024 October 1997 Insp Rept 50-293/97-08 on 970805-0913.No Violations Noted. Major Areas Inspected:Operations,Engineering,Maint & Plant Support ML20198L9231997-10-21021 October 1997 Insp Rept 50-293/97-05 on 970514-0828.Violations Being Considered for Escalated Enforcement Action.Major Areas Inspected:Engineering PNO-I-97-061, on 970922,util Informed Region I of Receipt of Internal Nuclear Safety Concern Potentially Involving Instance of Falsification of Control Room Log in 1989.Formal Investigation Initiated & Press Release Issued1997-09-23023 September 1997 PNO-I-97-061:on 970922,util Informed Region I of Receipt of Internal Nuclear Safety Concern Potentially Involving Instance of Falsification of Control Room Log in 1989.Formal Investigation Initiated & Press Release Issued ML20211A2741997-09-17017 September 1997 Notice of Violation from Insp on 970721-0801.Violation Noted:For Problem Rept PR97.9220,trip of B Residual Heat Removal Pump,Individual Performing Root Cause Analysis Was Not Formally Trained in HPI Methodology IR 05000293/19970071997-09-15015 September 1997 Insp Rept 50-293/97-07 on 970625-0816.No Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000293/19970801997-09-12012 September 1997 Insp Rept 50-293/97-80 on 970721-0801.Violations Noted.Major Areas Inspected:Effectiveness of Processes for Identifying Resolving & Preventing Issues That Degrade Quality of Plant Operations & Safety ML20216G8181997-09-0404 September 1997 Insp Rept 50-293/97-09 on 970827-28.No Violations Noted. Major Areas Inspected:Licensee Access Authorization Program PNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997 PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR IR 05000293/19970041997-08-0707 August 1997 Insp Rept 50-293/97-04 on 970505-23.No Violations Noted. Major Areas Inspected:Effectiveness of Licensees Efforts in Maintaining Design Basis of safety-related Sys ML20149K0431997-07-22022 July 1997 Insp Rept 50-293/97-03 on 970429-0624.Violations Noted. Major Areas Inspected:Operations,Maintenance,Engineering & Plant Support ML20149K0401997-07-22022 July 1997 Notice of Violation from Insp on 970429-0624.Violation Noted:On 970602,station Services Dept Worker Tied Open Boiler Room Door Which Forms Part of Radiologically Controlled Area & Action Not Directed by RP Personnel ML20149K1311997-07-18018 July 1997 NRC Operator Licensing Exam Rept 50-293/97-06 (Including Completed & Graded Tests) for Tests Administered on 970505-09 ML20149K1291997-07-18018 July 1997 Notice of Violation from Exam on 970505-09.Violation Noted: Two SRO Applications Dtd 970418,documented Five Manipulations Based on Credit Taken for Multiple Manipulations Due to Power Change & One Should Be Credited ML20141K7861997-05-22022 May 1997 Insp Rept 50-293/97-02 on 970303-0428.Violations Noted. Major Areas Inspected:Operations,Maint,Engineering & Plant Support 1999-08-27
[Table view] |
Inspection Report - Pilgrim - 1987033 |
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U.S. NUCLEAR REGULATORY COMMISSION ,
REGION I l Report.N /87-33
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. Docket N License N DPR-35 Licensee: Boston Edison Company M/C Nuclear 800 Boylston Street-Boston, Massachusetts 02199 Facility Name: Pilgrim Nuclear Power Station Inspection At: Plymouth, Massachusetts .I
. Inspection Conducted: August- 3-7, 1987 1 i
j Inspectorsi ~ 4M L. Briggs, laid Reactor Engineer, DRS 8 /.s70 / # 7 date Approved by: / J , 'f 82d[<f 7 P.'Eselgr ' , Chief, Test Programs Section / ddte 08, DRS j Inspection Summary: Inspection on August 3-7, 1987 (Inspection Report i No. 50-293/87-33)
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Areas Inspected: Routine unannounced inspection of the licensee's post I modification test program preoperational test procedure review, QA/QC interface with post modification testing, independent verification and plant tour Results: One violation was identified for failure to adequetely review a design package and its associated post maintenance preoperational test, , l Paragraph !
Note: For acronyms not defined refer to NUREG-0544 " Handbook of Acronyms and l Initialisms". j l
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8708310211 870821 PDR ADOCK 05000293 G PDR
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DETAILS A"
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- M.'Akhtar,< Modifications Management Group Leader
- T. Beneduci, Senior Engineer, Modifications Management
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- N. Brosee, Outage Manager-
- R.,Grazio, FieM Engineering Sectinn Manager
- P. Hamilton, Cortpliance Group Leader
, ' * S, Hudson," Operations'Section Manager-
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' B. Lunn, Compliance Engineer
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" J..Mattia, QA, Group Leader
' * A. Morisi,- @ pt and Turnover Section Mantger
>2 l * K. Roberts, Station Nnager i
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- fN. Blumburg, Chief, Operational Programs'Section
- J. Lyash, Resident Inspector The inspector also contacted other memebers of the licensee'4 QA/QC and-technical stat ;
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- Denotes those present at the August 7, 1987, exit meetin ~
2.0' Post Modification Preoperational Testing (PMPT). Procedure Review l 2.1 Scooe
./ The PMPT's and Plant Design Changes (PDC's) listed below were
" 4 a' reviewed in preparation for test witnessin The PMPT's were j ' reviewed for, technical and administrative adequacy and for
. ,. f, , verification that testing is planned to adequately satisfy a regulatory svidance and licensee commitment They were also
, reviewed to vsrify licensee review and approval, proper format, test F
' objectives, prerequisites, initial conditions, test data recording requirements and system return to normal. The PDC's were reviewed to determine what changes were made to the associated system and to provide a bases for the determination of PMPT scope necessary to s verify the system's modified desig 'f
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PDC 86-70, Standby Gas Treatment System Modification; j
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PDC 82-25, 011 and Vibration Alarms Modification on )
Recirculation Pump Motors;
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PDC 85-59, HPCI Exhaust Vacuum Breaker;
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TP 87-128, Pre-Operational Test of Standby Gas Treatment System Modification Per PDC 86-70, Revision 1, dated July 20, 1987; r
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TP 86-95, Pre-Operational Test.of Oil Level and Vibration System on the Recirculation Pumps, Revision ~1, dated June 11, 1987;'and,
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TP.87-88, HPCI. Vacuum Breaker Pre-Operational Test, Revision 0 1, (draft).
2.2 . Discussion During the review of TP 87-128 the inspector noted several areas of the. test procedure that were either in error or. did not' appear. to verify the design of the modified system. These items were discussed with one of the licensee's senior Modifications Management Group (MMG) engineer The' engineer and licensee management agreed with the inspector that the following errors / omissions should tave been identifie Paragraphs 7.'2.5, 7.3.5 and 7.4.5 required 5 damper control switches- to be in the. auto position and their associated dampers in the open position. The associated dampers would be in the closed position with'the specified switch position and no initiation signal present, Section 7.3.8.and 7.3.8.9-did' not require verification tha't.
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valve A0N-112 closed when the 'B'. Standby' Gas Treatment System-(SBGTS)-fan tripped (per procedure). Inlet valve A0N-106 was verified as closin Paragraph 7.3.8.6 required the differential pressure across the calibrated orifice plate'(DPI-AA-32) in the 'B' SBGTS train to be recorded with the 'B' SBGTS fan in standby (off). This reading was being taken to measure 'B' train bypass flow so it could be combined with 'A' train to determine system flo Under the system conditions specified this reading would be zero ,
(0) since one of the SBGTS modifications moved the upstream i bypass flow connection such that the connection between the A ,
and B SBGTS trains is now downstream (bypassing) of the l'
calibrated orifice plat The flow recorded on the 'A'
calibrated orifice plant would represent full system flow ter ,
the specified lineu ~ Train 'B' logic requires A0N-106 damper (inlet) to open and '
pick up a position limit switch which allows the 'B' SBGTS fan to start and outlet damper A0N 112 to open. This logic sequence would occur during any start of the 'B' SBGTS train and was not- ;
checked in TP 87-12 The procedure did'not verify that per design the 'B' SBGTS i train would remain running after 20 minutes if the 'A' train
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p h-l had. insufficient flow or.was tripped with the 'B'. train in standby, The system is designed to trip the 'B' train after 20 minutes if sufficient flow exist The inspector discussed the above items with the licensee and reviewed the other TPs and PDCs identified in Paragraph 2.1 abov It_was. observed that the other PDCs provided a more defined level of testing requirements. PDC 86-70 did not specify any electrical or logic checks while PDC 85-59 and 82-25 did. The inspector noted that the Boston Edison Quality Assurance Manual-(BEQAM) Paragraph 3.3. and 3.3.2.8 specifically requires the cognizant design organization, in this case Boston Edison Nuclear Engineering Department (NED), to specify acceptance criteria and methods for verifying' design changes,
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such as qualification testin It was also noted that the Modifications Management Work Instruction Manual (MMWIM), dated January 12, 1987, in Section 10 requires the Maintenance Modification Group (MMG) to determine preoperational
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testing (POT) requirements and to prepare POTS to satisfy all aspects of required testin The inspector also observed that throughout the. entire review chain for this' PDC and TP that these deficiencies (lack of specified testing required to verify design and PMPT errors) were not identified and corrected. The licensee as part of their immediate correc+ive action statect that an independent, 3 man review group will be established, with no concurrent duties, to review PMPT's initiated for implementation during this outage .
The review of the remaining PMPT's did not'ider.tify any procedural deviations from the system design as described in the PD .3 Findings The above examples relative to PDC 86-70 and TP 87-128 constitute a violation of the requirements of 10 CFR 50 Appendix B, Criterion VI and BEQAM, Section 6, Document Control, for failure to perform an adequate review (293/87-33-01).
3.0 QA/QC Interface with Post Modification Testing 3.1 Scope The inspector requested all QC inspection reports (QCIR) associated with PDC 86-70 (SBGTS) and 82-25 (Recirculation Pump) which were implemented under maintenance requests 87-48-12 (SBGTS) and 86-2-49 j and 86-2-50 (Recirculation Pump). The following QCIR's were j provided the inspector. They primarily deal with the installation of i the modifications since testing of the modifications were in the l very early stages during this inspection, i
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QCIR 87-048-12A, Instrument Calibration (SBGTS) performed July 22, The QC inspector witnessed calibration of 2 separate
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1987 instrument loops being performed in accordance with an approved )
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procedure and also verified calibration status of all test equipment being use No deficiencies were noted by the QC inspecto QCIR 87-980, verification of correct installation of switch 42.1426-CS (SBGTS B train fan) performed August 2,1987. The QC inspector observed that the switch was installed in accordance with the PD )
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QCIR 87-14, Surveillance of the drilling of anchor bolt holes for hangers on the 41 foot 6 inch elevation of the reactor building, performed on January 6, 198 No discrepancies were observed by the QC inspecto QCIR's 87-75 and 87-81 concerned the witnessing of cables being pulled into the cable spreading room and into the control roo They were performed on January 27 and 28, 1987. No discrepancies were observed by the QC inspecto .3 Findings No violations were identified in the above revie .0 Independent Verification During the review discussed in Paragraph 2.2 the inspector independently calculated the various voltages required to give the desired vibration readings during the recirculation pump vibration monitor calibration check in TP 86-95. The inspectors calculations agreed with those contained in the procedur .0 Plant Tours The inspector toured various areas of the facility to assess plant and equipment conditions including cleanliness, fire hazards and work in progres No unacceptable conditions were observe .0 Exit Interview At the conclusion of the site inspection, on August 7, 1987, an exit interview was conducted with the licensee's senior site representatives (denoted iri Section 1). The findings were identified and inspection items were discusse _____- __ -
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At no time during this inspection was written material provided to the licensee by the inspector. Based on the NRC Region I review of this report and discussions held with licensae representatives during this inspection, it was determined that this report does not contain information subject to 10 CFR 2.790 restriction x l
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