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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar ML20005F2511990-01-0505 January 1990 Shoreham Nuclear Power Station Defueled Sar. ML17347B4621989-12-31031 December 1989 App a to USI A-46 & Generic Ltr 87-02. ML19332G1991989-09-18018 September 1989 Rev 0 to Radiological Safety Analysis for Spent Fuel Storage & Handling. ML20246D6871989-08-14014 August 1989 Rev 1 to Criticality Analysis of Byron & Braidwood Station High Density Fuel Racks ML18008A0311989-07-31031 July 1989 NTH-TR-01 Decrease in Heat Removal by Secondary Sys. ML19327B4011989-07-31031 July 1989 Safety Evaluation for Byron/Braidwood Stations Units 1 & 2 Transition to Westinghouse 17 X 17 Vantage 5 Fuel. ML20246D6711989-06-30030 June 1989 Criticality Analysis of Byron/Braidwood Fresh Fuel Racks ML20247H0711989-06-30030 June 1989 Description & Verification Summary of Computer Program, Gappipe ML20247H0791989-06-22022 June 1989 App to Description & Verification Summary of Computer Program,Gappipe ML20245E0181989-06-19019 June 1989 QC 1989 Staffing Rept ML20247N0621989-05-31031 May 1989 Production Training Dept,Braidwood,Malfunctions & Initial Conditions ML20247K3011989-05-12012 May 1989 Leak-Before-Break Evaluation for Carbon Steel Piping ML20247L1841989-05-12012 May 1989 Leak-Before-Break Evaluation for Stainless Steel Piping, Byron & Braidwood Nuclear Power Stations Units 1 & 2 ML18094A3551989-04-30030 April 1989 Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles. ML20247F1321989-03-23023 March 1989 Post-Tensioning Sys Evaluation,Callaway Unit 1 Containment & Wolf Creek Unit 1 Containment ML20005G4211989-02-28028 February 1989 Reactor Vessel Heatup & Cooldown Limit Curves for Normal Operation. ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20206C7451988-11-30030 November 1988 ATWS Mitigation Sys Specific Design for Byron/Braidwood Stations, Rev 5 ML20205T7501988-11-0404 November 1988 Detection & Skin Dose Evaluation for Characteristic X-Ray in Activation Product Contamination ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20154N6081988-09-30030 September 1988 Rev 1 to Identification of Unisolable Piping & Determination of Insp Locations ML20154K2091988-09-0909 September 1988 Rev 0 to Response to NRC Bulletin 88-005,Nonconforming Matls Supplied by Piping Supplies,Inc at Folsom,Nj & West Jersey Mfg Co.... Proprietary Procedure 1404.1, Leeb Hardness Testing (Equotip).... Encl.Procedure Withheld ML20153G8941988-08-31031 August 1988 Rev 1 to Shoreham Nuclear Power Station Prompt Notification Sys Rept ML20245B4181988-08-17017 August 1988 Investigation Rept,Design & Operation of Sampling Sys for Analysis of High Purity Water ML20196K6311988-06-29029 June 1988 QC Div 1988 Staffing Rept ML17347A7981988-06-16016 June 1988 Radiological Data Prepared for Resolution of USI A-46. ML17347A7971988-06-16016 June 1988 Seismic Hazard Data Prepared for Resolution of USI A-46. ML20150F2941988-05-31031 May 1988 Rev 4 to, ATWS Mitigation Sys Specific Design for Byron/ Braidwood Stations ML20196L6281988-05-20020 May 1988 Rev 2 to ATWS Mitigation Sys Actuation Circuitry (Amsac) ML20196L6421988-05-0606 May 1988 ATWS Mitigation Sys Actuation Circuitry Response to Unit Transients ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20148A4851988-02-29029 February 1988 Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys ML20151T4681988-01-31031 January 1988 Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness ML20148G5431988-01-15015 January 1988 Nonproprietary Mods to Critical Flow Model in RELAP5YA ML20155K1391987-12-30030 December 1987 Final Rept MSIV 3-Way Dual Solenoid Valve Failures ML20235F0881987-12-17017 December 1987 Marked-up Draft Seismological Analysis of Bodega Head,Ca ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235G3041987-09-29029 September 1987 Partially Withheld, Preliminary Investigation of Enrico Fermi II Nuclear Power Plant ML20235B3121987-08-31031 August 1987 Comparison of Monticello & Brunswick Recirculation Pump Trip ML18151A1351987-08-28028 August 1987 Rev 1 to SPDS SAR for VEPCO NUREG-0696 Computer Project, North Anna & Surry Nuclear Power Stations. ML20237K8201987-08-26026 August 1987 TVA Employee Concerns Special Program Bellefonte Nuclear Plant Element Rept BLN-NSRS-2, Review of Nuclear Safety Review Staff Non-Startup Items at Bellefonte ML20237K7691987-08-0606 August 1987 Rev 3 to TVA Employee Concern Special Program Browns Ferry Nuclear Plant Element Rept BFN-NSRS-1, Review of Nuclear Safety Review Staff Restart Items at Browns Ferry 1994-01-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1988-0171990-05-16016 May 1990 LER 88-017-01:on 881025,discovered That Seismic Monitoring Instrumentation Returned to Svc Prior to Verifying Sys Operability & Special Rept Not Written.Caused by Personnel Error.Surveillance Engineer Reassigned 05000322/LER-1988-0151990-05-16016 May 1990 LER 88-015-02:on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02:on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired 05000322/LER-1986-0141990-05-16016 May 1990 LER 86-014-01:on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153 1997-05-01
[Table view] |
Text
. _ .- . ... - -. _ - -
SNPS-1 FSAR f r
5.2.8 Inservice Inspection Proaram j
The reactor pressure vessel, system piping, pumps, valves, and as defined by the components which require inservice inspection, Code, Section XI and all ASME Boiler and Pressure Vess el addenda thereto, hereinafter called ASME XI, are applicable with the objective of full designed, fabricated, and erected compliance with the requirements of ASME XI and its addenda in six months prior to date of issuance of the construction
+
etfect pennit as stated in Title 10 of the Code of Federal Regulations, Pa rt 50.55a, paragraph (g). (10CFR50) Addenda to ASME XI become ef f ective six months af ter date of publication. Thus, for the Shoreham plant, the addenda in effect six months prior to date of of ASME XI issuance of construction permit is the 1971 edition However, the Shoreham design through the Winter 1971 addenda. of the 1971 for inservice inspection is based on requirements l
edition of ASME XI through the Summer 1972 addenda.
5.2.8.1 Provisions for Access to the Peactor Coolant Pressure Boundary
\
The Shoreham plant was already in an advanced stage of of design and ASME XI 4
fabrication when inservice inspection requirements effective. Theref ore, f ull compliance was not practical.
Gtbecame is the intent of the 6esign to comply as fully as practical.
and components which require inspection in accordance r
Systems designed with adequate with the requirements of ASME XI are physical access to allow the required inspection.
Piping systems requiring volumetric ultrasonic inspection are are physically designed so that welds requiring inspection accessible for inspection with ultrasonic equipment.these welds
- Access is l provided by leaving adequate space around pipes at
) and by means of renovable insulation and shielding as required.
exa.nination are The surfaces of welds requiring ultrasonic smoothed and contoured to permit effective use of ultrasonic l
i transducers, and pipes adjacent to fittings- are arranged to permit meaningful examination by avoidance of irregular or surface
' visual geometries. Piping systems reauiring surface examination are designed to allow access and visibility adequate for performance of such examinations.
- The following areas of the reactor vessel are available for visual and/or nondestructive inservice examination
- 1. Full penetration pressure containing welds in the j
following areas:
I I
Vessel shell external surface.
I Reactor vessel nor le exterior surf aces.
Closure head inside and outside surfaces.
- h92830829 5..'-39 HAFNER83-386 pg ;
g.n uc b-jeg UNITED STATES n NUCLEAR REGULATORY COMMISSION
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Docket No. 50-322 1980 OCT 8 Long Island Lighting Company
. ATTN: Mr. Andrew W. Wofford Vice President 175 East Old Country Road Hicksville, New York 11801 Gentlemen:
Subject:
Inspection 50-322/80-14 This refers to the inspection conducted by Mr. J. C. Higgins of this office on August 11-September 14, 1980 at Shoreham Nuclear Power Station, Shoreham, New York of activities authorized by NRC License No. CPPR-95 and to the discussions of our findings held by Mr. Higgins with Mr. Gerecke and other members of your staff periodically during the inspection.
Areas examined during this inspec; ion are described in the Office of Inspection and Enforcement inspection Report which is enclosed with this letter. Within these areas, the. inspection consisted of selective examinations of procedures O
and representative records, i.nterviews with personnel, and observations by the inspector.
Based on the results of this inspection, it appears that one of your activities was not conducted in full compliance with NRC requirements, as set.forth in the Notice of Violation, enclosed herewith as Appendix A. This item of noncompliance has been categorized into the levels as described in our correspondence to you dated December 31. 1974. This notice is sent to you pursuant to the provisions of Section 2.201 of the NRC's " Rules of Practice," Part 2, Title'10, Code of Federal Regulations. Although Section 2.201 requires you to submit to this office, within 20 days of your receipt of this notice, a written statement of explanation, we note that this item of noncompliance was ' corrected prior to the completion of our inspection, and therefore, no response with respect to this matter is required.
P J
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DCT 8 1980 Long Island Lighting Company- 2 r,
In accordance with Section 2.790 of the NRC's " Rules of Practice", Part 2 U Title 10, Code of Federal Regulations, a copy of this letter and the. enclosures will be placed in the NRC's Public Document Room. If this report contains any information that you (or your contractor) believe to be proprietary, it is necessary that you make a written application within 20 days to this office to withhold such information from public disclosure. Any such application must be accompanied by an affidavit executed by the owner of the information, which identifies the document or part sought to be withheld, and which contains a statement of reasons which addresses with specificity the items which will be considered by the Commission as listed in subparagraph (b) (4) of Section 2.790.
The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit. If we do not hear from you in this regard within the specified period, the rcoort will be pla ed in tne Public Document Room.
Should you have any questions concerning this inspection, we will be pleased to discuss them with you. l Sincerely, c -
Eldon J. Brunner, Chief Reactor Operations and Nuclear Support Branch
Enclosures:
l l
- 1. Appendix A, Motice of Violation
- 2. Office of Inspection and Enforcement Inspection Report Number 50-?22/80-14
)
cc w/encls:
J. P. Novarro, Project Manager Edward M. Barrett, Esq.
Edward J. Walsh, Esq. l T. F. Gerecke, Manager, Engineering QA Department bcc w/encls:
IE Mail S Files (For Anorcoriate Distribution)
Central Files Public Pocu ent Room (enn) local Public Doctrent %on (LonO Nuclear Safety Information Center (?! SIC)
Technical Infornation Center (TIC)
"Eq:I Readina "com state of New York James C. Hiecins, %sident Inspector L. Narrow, RCTJS nranch O a '> i ' s o a . ""' m"
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U.S. NUCLEAR RECULATORY COMMISSION -
0FFICE OF INSPECTICN AND ENFORCEMENT
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Region I ,
'J.?.x 50-322 /80-14 rep 0f.;0 %.f .f; Ocy, 8 50-322 4 Docket No. % ,,4 'n.,,
Pricrity -- Category B License No. CPPR-95 Licensee: Lor.c Island Lichtinc Comoanv 175 East' Old Country Road Hicksville. New York 11801 .
Facility Name: Shoreham Nuclear Power Station, Unit 1 Inspection at: Shoreham, New York Inspection concu ed: August 11 - September 14, 1980 Inspectors: /' _w /d / i' d cate signec
.' C'. pins, Resident Inspector
~
eate signed O
care signed
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Approved by: __
tade signed fi. B. Kistb, Chief, Reactor Projects Section No. 4, RO&NS Branch .
Inscection Su=arv:
Inspactions on: August 11-September 14,1980 (Inspection Report No. 50-322/80-14)
Areas Inspected: Routine onsite regular, backshift and weekend inspections by the resident inspector (110. inspection hours) of work activities, preoperational testing,
- and plant staff activities including
- tours of the facility; test witnessing; comparison of as-built plant to FSAR descriptions; review of test.and operating procedures, review of IE Bulletins and Circulars; review of p' ant drawings; review of implementation of preoperational program; and, followup on previous inspection.
findings. -
Results: Of the eight areas inspected, no items of noncomplianc.e were identified in seven areas and one 'in theeighth area (infraction - installation of vent lines and valves without an authorizing E & DCR, paragraph.12.b).
7
- a 79g-Region I For:.12 I (Rev. April 77) 4 L: -
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APPENDIX A NOTICE OF VIOLATION Long Island Lighting Company DocketNo.50$22 l ,
This refers to the inspection conducted by a representative of the Region I (Philadelphia) office at the Shoreham Nuclear Power Station, Shoreham, New York, of activities authorized by NRC Construction Permit No. CPPR-95.
During this inspection conducted on August 11-September 14, 1980, the following apparent item of noncompliance was identified. This item is an infraction.
Criterion III of Appendix B of 10 CFR 50 states, in part, that " Measures shall be established for the identification and control of design interfaces and for coordination among participating design organizations. These measures shall include the establishment of procedures among participating design organizations for the review, approval, release, distribution, and revision of documents involving design interfaces". The Shoreham Nuclear Power Station FSAR Section 17.1.3A requires that organizations having design responsibility establish written procedures for control of their activities. Stone & Webster (S&W) Engineering Assurance Procedure 6.3, paragraph 2.1 states that Engineering & Design Coordination Reports (E&DCR's) shall be used to document changes to S&W drawings. Courter & Company, Inc. Quality Assurance Procedure QAP 15.3, paragraph 3.2.a states that the designer shall determine if a field l change constitutes a deviation from the latest approved engineering design 'i and process ?.o E&DCR if required.
Contrary to the above vent lines and vent valves not specified on the S&W drawing (FM-25A) were installed in three locations of the High Pressure l Coolant Injection System without an authorizing E&DCR to modify the drawing.
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DETAILS
- 1. Persons Contacted _
J. Carney, Site Engineering Representative (S&W)
D. Durand, 0QA. Engineer (L)
T. Gerecke, QA Manager (L)
R. Gutmann, Maintenance Engineer (L)
J. Kelly, Field QA Manager (L)
W. Hunt, Systems Superintendent (L)
W. Klein, Lead Startup Engineer (L)
M. Milligan, Project Engineer (L)
J. Morin, Senior Licensing Engineer (L)
E. Nicholas, Section Supervisor, FQA (L)
J. Novarro, Project Manager (L)
R. Perra, Chief Inspection Supervisor (S&W)
J. Rivello, Plant P ager (L)
W. Steiger, Chief eratingEngineer(L)
J. Taylor, Startup Manager (L)
D. Terry, Lead Startup Engineer (L)
L - Long Island Lighting Company S&W - Stone and Webster The inspector also interviewed other license and contractor personnel during the course of the inspection including management, clerical, maintenance, operations, engineering, testing, quality assurance, and construction personnel.
- 2. Previous Inspection Item Update (open) Unresolved Item (322/80-0a-04): Vendor Procedures: The licensee's representative stated that any vendor procedure used to. satisfy FSAR preoperational test requirements would be required to be reviewed by the Joint Test Group (JTG) by commitments directly in the FSAR. This -
was emphasized to all Lead Startup Engineers by a memo from the Startup Manager dated 9/11/80. This item remains open pending review by the JTG of the Carbon and HEPA filter test procedures discussed in the item.
(closed) Unresolved Item (322/80-04-05): Preoperational Test (PT)
Procedure for Control Roam Air Conditioning (CRAC) System: The various flow rates discussed in this item will be tested via procedure CG-000.034-1.
Revision 1 to PT.412.001 was issued to incorporated the other concerns, namely a specific acceptance criteria, test of the automatic start feature of Fan 25 and a demonstration of the capability to manually close certain valves within the time frame assumed in dose calculations given in the FSAR.
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- - - - - . . . . . . . . - m. - w.
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- 3. Plant Tour O The inspector conducted periodic tours of accessible areas in the plant V during normal, backshift, and weekend hours. During these tours, the following specific items were evaluated:
-- Hot Work. Adequacy of fire prevention / protection measures used.
-- Fire Equipment. Operability and evidence of periodic inspection of fire suppression equipment.
-- Housekeeping. Minimal accumulations of debris and maintenance of required cleanness levels of systems under or foilowing testing.
-- Component Tagging. Implementation and observance of equipment tagging for safety, equipment protection, and jurisdiction.
-- Instrumentation. Adequate protection for installed instrumentation.
-- Logs. Completeness of logs maintained.
-- Securi ty. Adequate site construction security.
-- Prohibited Items. Observations to determine m smoking in restricted areas and no alcoholic beverages on site.
-- Weld Rod Control. Observations to determine weld rod was being controlled in accordance with site procedures.
C- .
Minor problem areas in weld rod control and housekeeping were discussed with licensee rapresentatives throughout the inspection.
No items of noncompliance were identified.
- 4. Maintainability The inspector reviewed a letter from A. W. Wofford to C. Davis, J. Oye and J. Gum:nersall titled "Shoreham Maintainability" dated 3/16/79, which sets up a Maintainability Task Force. The purpose of this task force is to identify via system and area walk-downs potential maintenance problems.
This is currently a coordinated effort between LILCO, Stone & Webster, and General Electric. To date about 1600 items have been identified. The licensee tracks these items on a computer and dispositions them as the program proceeds. A number of equipment modifications have already been completed.
During plant tours the inspector noted that valves 1821
- HV-055A and B, eighteen inch manually operated valves in the feedwater lines,tre located in a potentially significant radiation area in the primary containment and would require many minutes for an operator to manually operate them. These I valves are used for maintenance isolation purposes. The inspector questioned whether the concept of maintaining radiation doses as low as (m,! reasonably achievable (ALARA) had been considered when making these valves manually operated. This item is designated as inspector follow item no. (322/80-14-01).
i L