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| {{Adams | | {{Adams |
| | number = ML20244C381 | | | number = ML20247L276 |
| | issue date = 05/26/1989 | | | issue date = 07/18/1989 |
| | title = Insp Repts 50-498/89-11 & 50-499/89-11 on 890401-30. Violations Noted.Major Areas Inspected:Plant Status,Followup of Events,Operational Safety Verification,Monthly Maint Observation & Surveillance Observation | | | title = Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-11 & 50-499/89-11 |
| | author name = Holler E | | | author name = Milhoan J |
| | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| | addressee name = | | | addressee name = Goldberg J |
| | addressee affiliation = | | | addressee affiliation = HOUSTON LIGHTING & POWER CO. |
| | docket = 05000498, 05000499 | | | docket = 05000498, 05000499 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = 50-498-89-11, 50-499-89-11, NUDOCS 8906140240 | | | document report number = NUDOCS 8908010200 |
| | package number = ML20244C372 | | | title reference date = 06-16-1989 |
| | document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | page count = 14 | | | page count = 3 |
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| | JLI8IW i In Reply Refer To: |
| ' * | | Dockets: 50-498/89-11 50-499/89-11 |
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| . | | Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vic President, Nuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen: |
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| | Thank you for your letter of June 16, 1989, in response to our letter and Notice of Violation dated June 7, 1989. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine |
| APPENDIX B
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| | Sincerely, Original Signed D3 |
| U.S. NUCLEAR REGULATORY COMMISSION
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| , - REGION IV
| | James L. Milhoan, Director Division of Reactor Projects cc: |
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| | Houston Lighting & Power Company ATTN: M. A. McBurnett, Manager Operations Support Licensing P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: Gerald E. Vaughn, Vice President Nuclear Operations P.O. Box 289 Wadsworth, Texas 77483 RIV:DRP/Dh C:DRP/ :DRPw DMHunnicutt;df EJHoller' 4.JCa''=fMn3LMAn- O! |
| .NRC Inspection Rcport: 50-498/89-11 Operating Licenses: NPF-76 50-499/89-11 NPF-8 Dockets: 50-498 50-499 e
| | 7/18 /89 7/g/89 7/)f/89 |
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| Licensee: Houston Lighting & Power Company (HL&P)
| | 8908010200 890718 |
| P.O. Box 1700 Houston, Texas 77001 Facility Name: South Texas Project (STP), Units 1 and 2 Inspection At: STP, Natagorda County, Texas | | .PDR ADOCK 05000498 O F O'.- |
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| Inspection Conducted:' April 1-30, 1989 !
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| Inspectors: J. E. Bess, Senior Resident Inspector, Uni l Project Section D, Division of Reactor j Projects ,
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| J. I. Tapia, Senior Resident Inspector Unit 2, Project Section D, Division of Reactor ! | | . , . ....; |
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| | Houston Lighting & Power Company -2-Houston Lighting & Power Company ATTN: J. T. Westermeier, General Manager South Texas Project P.O. Box 289 Wadsworth, Texas 77483 Central Power & Light Company ATTN: R. L. Range /R. P. Verret P.O. Box 2121 Corpus Christi, Texas 78403 City of Austin Electric Utility ATTN: R. J. Miner, Chief Operating Officer (2 copies) |
| | 721 Barton Springs Road Austin, Texas 78704 ; |
| | Newman & Holtzinger, ATTN: J. R. Newman, Esquire 1615 L Streat Washington, Houston Lighting & Power Company ATTN: S. L. Rosen P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: R. W. Chewning, Chairman Nuclear Safety Review Board j P.O. Box 289 Wadsworth, Texas 77483 City Public Service Board ATTN: R. J. Costello/M. T. Hardt P.O. Box 1771 ' |
| | San Antonio, Texas 78296 i |
| | Houston Lighting & Power Company ATTN: Licensing Representative- l Suite 610 Three Metro Center Bethesda, Maryland 20814 Houston Lighting & Power Company ATTN: Rufus S. Scott, Associate General Counsel P.O. Box 1700 Houston, Texas 77001 i |
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| Projects l i
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| R. J. Evans, Resident Inspector, Unit 1 ';
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| Project Section D, Division of. Reactor
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| , D. L. Garrison, Resident Inspector, Unit 2 :
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| Project Section D, Division of Reactor ,
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| R. V. Azua, Reactor Inspector, Test Program
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| | ; Houston' Ligh' ting &. Power Company -3- , - |
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| | Records' Center . - |
| | - 1100 Circlev75 Parkway . , |
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| | -Atlanta,. Georgia- 30339-3064: |
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| Section, Division of Reactor Safety j i
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| ' | | . Dr. lo'seph M. Hendrie t50.Be11 port Lane |
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| | Bellport,;New York 11713 m ; Texas Radiation Control- Program Director |
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| | ,bec.toDMB(IE01) |
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| | bec4istrib.lbyRIV: . |
| | DRP. ' . RRI SectionChief,(DRP/D)' |
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| | DR l MIS System . . |
| | RPB-DRSS Lisa Shea,!RM/ALFJ RIV Fil R.!Bachmann OGC' . |
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| | RSTS Operator |
| | : G.L Dick, NRR. Project Manager (MS:- 13-D-18)' R. D. Martin Project' Engineer (DRP/D).. |
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| Approved: ( _
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| E. J. Holler, Chief, Project Section D Date l Division of Reactor Projects i i
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| 890614o240 890607 POR ADOCK 05000498 Q FDC
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| 1 Inspection Summary l Inspection Conducted April 1-30, 1989 (Report 50-498/89-11; 50-499/89-11)
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| Areas Inspected: Routine, unannounced inspection of plant status, followup of events, operational safety verification, monthly maintenance observation, and monthly surveillance observatio Results: Within the areas inspected, one violation of NRC requirements was identified regarding failure to establish environmental qualification of certain auxiliary feedwater system valves with installed space heaters. Also, the circuitr paragraph 4)yAofweakness
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| the spacewasheaters noted did notcontrolling in the meet the ofguidance of manuals, instruction RG 1.75 (see spare parts, history files, and housekeeping. A violation was noted but not cited regarding maintenance activities (see paragraph 5). Discrepancies were noted between the same procedures used in Unit I and in Unit 2 regarding accumulator surveillance (see paragraph 6). Discrepancies regarding proper maintenance of oil level in the essential chillers was also noted (see paragraph 7).
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| DETAILS l
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| l . Persons Contacted
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| *P. L. Walker, Senior Licensing Engineer
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| *J. E.. Geiger, General Manager, Nuclear Assurance
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| *A. W. Harrison, Supervising Licensing Engineer
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| *V. A. Simonis, Plant Operations Support Manager
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| *S. M. Head, Supervising Licensing Engineer
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| *M. R. Wisenburg, Plant Superintendent
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| *J. R. Lovell Technical Services Manager
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| *W. H. Kinsey, Plant Manager
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| *M. A. McBurnett, Licensing Manager In addition to the above, the NRC inspectors also held discussions with various licensee, architect engineer (AE), maintenance, and other contractor personnel during this inspectio * Denotes those individuals attending the exit interview conducted on May 4, 198 . Plant Status Unit 1 operated at full licensed thermal power for the duration of this inspection period. The annual emergency preparedness graded exercise was conducted on April 26, 1989. The results of the exercise are documented in NRC Inspection Report 50-498/89-12; 50-499/89-1 Unit 2 began this inspection period at 8 percent reactor power. After an initial unsuccessful attempt to synchronize the Unit 2 main generator to the offsite electrical distribution system, the licensee successfully synchronized the generator on April 11, 1989. Toward the end of the inspection period, the licensee shut down Unit 2 to find and correct a noise essociated with the main turbin . Followup of Events - Units 1 and 2 (93702)
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| On April 6,1989, at 5:54 a.m. , with the Unit 1 emergency safety features (ESF) Diesel Generator (DG) No.11 out of service for scheduled i maintenance, ESF DG No.12 failed to start during an operability test required by Technical Specification (TS) 3.8.1.1. With two inoperable DGs, Unit 1 entered a 2-hour limiting condition for operation (LCO) as required by TS 3.8.1.1(f). Unable to return DG Nos.11 or 12 to i
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| operability status by 7:54 a.m., the licensee began a controlled shutdown of Unit 1 as requireo by TS 3.8.1.1(f).
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| The problem with the DG No.12 was determined to be a failed resistor in the governor assembly. The licensee had received information from the i Palo Verde Nuclear Generating Station (PVNGS) that similar problems had
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| existed with their DGs. Both the STP and the PVNGS DGs were manufactured by Cooper Energy Services. The licensee contacted the manufacturer to 1 discuss the problem and to pursue possible corrective measures that should preclude recurrence of this even At 11:46 a.m., on April 6,1989, DG No.11 was returned to service. The NRC inspector witnessed the performance of Procedure 1 PSP 03-DG-0001,
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| " Standby (S/B) Diesel Generator No.11 Operability Test." Following the replacement of the failed resistor in the governor assembly and after successfully completing the required operability test, the licensee declared DG No.12 operable at 7:50 p.m. and exited TS 3.8. On April 5,1989, Unit 2 tripped from 11 percent reactor power while attempting to synchrntize the main generator to the offsite electrical distribution system. The licensee determined the cause of the reactor trip to be an electrical relay problem associated with the main generator circuit breaker. The licensee determined that improper implementation of changes to the wiring of the generator backup distance relay and negative phase sequence relay by startup technicians, prior to turnover of the generator system to plant operations, caused the Main Generator Circuit Breaker to trip. The problem relsys were rewired and tested on April 7, 198 The loss of power to 13.8kV auxiliary buses, after the generator circuit breaker tripped, resulted in a loss of power to Reactor Coolant Pumps 2A, 2B, 2C, and 2D. The undervoltage coils on the pump breakers actuated to trip the breakers and generate a low flow reactor trip signal through the Solid State Protection System, which tripped the reactor. All rods inserted normally. The loss of power to ESF bus E2A caused Standby Diesel Generator No. 21 to start. ESF loads sequenced onto the bus as require After verifying stable conditions, the operators reenergized the auxiliary buses from their respective standby buses which were supplied from the Unit 2 Standby Transformer. When bus 2J was reenergized, RCP 2D restarted because its breaker had failed to trip open on the loss of voltage. The additional flow caused a drop in steam generator water level resulting in an actuation of the Auxiliary Feedwater system. Average coolant temperature continued to decrease due to lack of decay heat, lack of coolant pump heat, and secondary steam loads. A main steam isolation was manually initiated to prevent overcooling of the RC Troubleshooting of the RCP 2D breaker revealed a broken lug on a cable from the undervoltage coil to the breaker trip circuit. The wita connected to the lug had caught on the breaker enclosure, apparently when the breaker was racked in, because of the wire falling out of its harnes The undervoltage coil functioned properly and sent a trip signal to the Solid State Protection System to initiate a reactor trip; however, the RCP breaker did not trip because of the broken lug. The broken lug on the RCP 2D breaker was replaced and the other Unit 2 RCP breakers were checked for other wires which may have fallen from their harnesse i
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| | The Light N |
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| | Houston Lighting k Power P.O. Box 1700 Houston. Texas 77001 (713) 228 9211 June 16, 1989 ST-HL AE-3141 File No. G02.04 _ ' |
| | 10CFR2.20 . |
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| | U. S. Nuclear Regulatory Commission 3@ |
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| | Attention: Document Control Desk |
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| | Washington, DC 20555 jhi O{- |
| | South Texas Project Electric Generating Station |
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| | Units 1 & 2 Docket Nos. STN 50-498. STN 50-499 Resnonse to Notice of Violation (498/8911-01: 499/8911-01) |
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| | Houston Lighting & Power Company has reviewed Notice of Violation (498/8911-01; 499/8911-01) dated June 7,1989, and submits the attached response pursuant to 10CPR2.20 If you should have any questions on this matter, please contact Mr. M. A. McBurnett at (512)972-853 / |
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| | G. E. Vaughn Vice President Nuclear Operaticns CEV/PLV/eg Attachment: Response to Notice of Violation (498/8911-01; 499/8911-01) |
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| . Plant restart was delayed by a packing leak on _a feedwater isolation bypass valve. Mode I was achieved on April 11, 1989. On the same day, at 1:26 p.m., initial generator synchronization to the offsf te electrical distribution system was achieve On April 15,1989, a Unit 2 reactor trip occurred when the Train S reactor trip breaker opened without receiving a reactor trip signal from the solid state protection system. All systems functioned normally after the tri The faulty breaker was subsequently replaced but reactor restart was again delayed by necessary repairs to a worsening packing leak on the feedwater isolation bypass valve. Mode 1 was again achieved on April 20, 198 On April 21, 1989, a metallic noise was discovered in the area near the No. 8 main turbine generator bearing. HL&P commenced a reactor shutdown to disassemble and inspect the low pressure turbine and bearings. On April 27,1989, the licensee determined that a bore plug in the main turbine generator jack shaft had backed out and fallen into the hollow bull gear, causing a noise as it tumbled within the bull gear when the turbine was rolled. The inspection period ended with reassembly of the main turbine ongoin . Operational Safety. Verification - Units 1 & 2 (71707)
| | 1 A1/049.NL2 A Subsidiary of Houston Industries Incorporated u $ 9-250 |
| The objectives of this portion of the inspection were to ensure that the facility was being operated safely and in conformance with regulatory requirements, to er.sure that the licensee's management controls were effective in discharging the licensee's responsibility for continued safe operation, and te assure that selected activities of the licensee's radiological protection program were implemented in conformance with plant policies and procedures and were in compliance with the approved physical security pla The NRC inspectors visited the control rooms on a daily basis when onsite and verified that control room staffing, operator behavior, shift turnover, adherence to TS LCOs, and overall control room decorum were being conducted in accordance with NRC requirement Tours were conducted throughout various locations of the plant to observe work and operations in progress. Radiological work practices, posting of barriers, ard proper use of personnel dosimetry were observe The NRC inspectors verified, on a sampling basis, that the licensee's security force was functioning in compliance with the approved physical security plan. Search equipment such as X-ray machines, metal detectors, and explosive detectors were observed to be operational. The NRC inspectors noted that the protected area was well maintained and not compromised by erosion or unauthorized openings in the area barrie General housekeeping, cleanliness, and physical condition of safety-related equipment were inspected with particular emphasis on engineered safety feature (ESF) system _ _ - _ _ _
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| | Ilouston 1.ighting & Iber Conilun) |
| | g ST-HL-AE-3141 File N CO2.04 Page 2 cc: |
| | Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston I.ighting & Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 George Dick, Project Manager U. S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 Circle 75 Parkway Jack E. Bess Atlanta, CA 30339-3064 Senior Resident Inspector - Unit I c/o U. S. Nuclear Regulatory Commission Dr. Joseph M. Hendrie P. O. Box 910 50 Be11 port Lane Bay City TX 77414 Be11 port, NY 11713 ~ |
| | J. I. Tapia Senior Resident Inspector - Unit 2 c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, P. L Street, N. Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 Copies) |
| | Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 12/21/88 A1/049.NL2 |
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| During the inspection period, the NRC inspectors questioned the licensee about the use of space heaters in safety-related motor operated valve The licensee identified seven safety-related valves per unit with space heaters.. Three valves were associated with the Essential Cooling Water (ECW) system and four were associated with Train D of the Auxiliary Feedwater(AFW) system. Space heaters for the valves were provided by the vendor for use during reinstallation storage and were not considered safety related. After questioning by the NRC inspectors on the safety classification of the motor space heaters, the licensee perfonned an indepth review of the application of space heaters in the seven valve The licensee determined that the space heaters were incorrectly wired into I the circuitry of the eight (four per unit) AFW valves but were correctly I wired into the circuitry of the six (three per unit) ECW valves. The six ECW valve space heaters were wired with dual circuit breakers, with one-breaker designed to shunt trip open on an ESF signal. However, the eight AFW valves had nonsafety-related space heaters wired in parallel to the Class IE 125V DC motors. The wiring confi criteria established by Regulatory GuideRG).1.75,"Ph (guration apparently did not meet of Electrical Systems." The four AFW valves (per unit)ysical are: AF-MOV0143, Independence AFW turbine steam inlet valve; AF-MOV0514, AFW Pump 14 turbine trip and throttle valve; AF-FV7526, AFW to steam generator ID regulating valve; and AF-M0V0019, AF turbine Pump 14 isolation valv The eight AFW valves were located in the Unit 1 and Unit 2 isolation valve cubicle (IVC) buildings. The area would be subjected to a harsh environment if a design basis accident occurred. The eight AFW valves were environmentally qualified because of their location. Vendor supplied documents (Wyle Laboratories Report No. 47644-05) indicated that the motor operated valves were tested for environmental qualification (EQ) without the space heaters being energized. The licensee operated the eight EQ AFW valves for several months with space heaters wired into the valve circuits, even though the space heaters had not been shown to have been EQ teste Paragraph (f) of 10 CFR 50.49 requires that qualification of each component must be based on testing or experience with identical equipment, or with similar equipment with a supporting analysis, to show that the equipment to be qualified is acceptable. Paragraph (k) of 10 CFR 50.49 states that equipment previously required by the Commission to be qualified to NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety Related Electrical Equipment," need not be requalified. Section5(1)ofNUREG-0588, Revision 1,statesthatthe qualification documentation shall verify that each type of electrical equipment is qualified for its application and meets its 'specified performance requirements. The basis of qualification shall be explained to show the relationship of all facets of proof needed to support adequacy of the complete equipment. Data used to demonstrate the qualification of the equipment shall be pertinent to the application and organized in an auditable for _ _ _ _ . _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - _ -
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| | g Attachment ST HL- AE 3141 1 Page 1 of 3 South Texas Project Electric Generating Station Units 1 & 2 4 Docket Nos. STN 50-498, STN 50 499 Response to Notice of Violation (498/8911-01: 499/8911-01) ) |
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| | 1 Statement of Violation |
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| | 10CFR50.49, paragraph (f) requires that (environmental) qualification of each component m ~ust be based on testing or experience with identical equipment, or with similar equipment with a supporting analysis, to show that the equipment to be qualified is acceptabl Paragraph (k) of 10CFR50.49 states that equipment previously required by the Commission to be qualified to NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," - |
| | need not be requalifie Paragraph 5(1) of NUREG-0588 states that the qualification documentation shall verify that each type of electrical equipment is qualified for its application and meets its specified performance requirements. The basis of qualification shall be explained to show the relationship of all facets of proof needed to support adequacy of the complete equipmen Data used to demonstrate the qualification of the equipment shall be pertinent to the application and organized in an auditablo for Contrary to the above, the equipment qualification file, which contained Wyle Laboratories Report No. 47664-05, " Assessment Report on Limitorque Operators For Use in South Texas Nuclear Power Plant," for eight auxiliary feedwater valves with space heaters installed and energized, did not support qualification. This was due to the failure to analyze all possible effects of energized space heaters used within the motor operator. No analyses were contained in the files to fully establish qualification for air temperature rises of cables, wires, splices, and components resulting from their proximity to the heater I Houston Lir_htine & Power Positior HL4R concurs that the cited violation occurred. |
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| : The equipment qualification file (Wyle Laboratories Report No. 47664-05)
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| for the eight AFW valves did not adequately support the actual application of the valves with the space' heaters installed and energized. The EQ documentation' failed to adequately analyze for all possible effects of energized space heaters used within the valve assemblies. Specifically, the areas not analyzed included effect of premature aging of the valve com)onents due' to: the additional heat supplied by the heater. .the effect-of leater failure on the valve, and the effect of burn damage o electrical components due to close proximity to the heater element Failure to properly qualify the eight AFW valves-with regard to their
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| ~ application.in the field is an apparent violation of 10 CFR 50.49
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| . requirements (50-498/8911-01;50-499/8911-01)._
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| Train B of the Safety Injection (SI) system for Unit 2 was inspected to ensure the system valves, control switches, and electrical power supplies were in their correct positions, as required by the system operating
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| . procedure and plant drawings. The SI system Train B was compared to Procedure 2 POP 02-SI-0002, Revision 2, " Safety Injection System Initial Lineup," and the Piping and Instrument Diagram (P&ID) 5N129F05014 No. 2, Revision.10 " Safety Injection System." All valves, power supplies, and-control switches were found to be in the correct ' position for the mode of operation on the day of inspection. Items observed during the inspection included:
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| Labelling discrepancies were observed throughout the system lineup .For example, in the Control Board Lineup 2 POP 02-SI-0002-5, Valve 2-SI-FV-3957 was labelled "HHSI Tc Upstream" on the panel, but was called "HHSI Pump Cold Leg Test Line Isolation Valv, in the
| | ST-HL-AE-3141 Page 2 of 3 i |
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| | South Texas Project Electric Generating Station Units 1 & 2 Docket Nos. STN 50-498, STN 50 499 Response to Notice of Viqlation (498/8911-01: 499/8911-01) |
| procedure. In the electrical lineup, the field label for Device E2B1-WIL was " Backup Breaker For Compt. C1," but E2B1-WIL was I
| | III. Reason for Violation The cause of this violation is failure of design personnel to recognize the need to disconnect the space heaters. This resulted from the fact that normally, heater elements are wired to a terminal strip on points separate from the wiring of the motors and the limit and torque switches. However, in the case of these DC-operated MOVs, the motor beater element leads were connected by the vendor to the same points on the terminal strip used in wiring the motor leads. Design personnel only evaluated the seismic qualification impact of the space heaters, "" |
| called 2-SI-M0V-0006B in the procedur In Train B Initial Lineup Procedure 2P0P02-SI-0002-5, the location of Device 2-SI-0070B was missing the room number (fuel handling building (FHB) RM-5).
| | and did not consider the environmental impact of the heaters on operability of the valves. Consequently, the heater elements were It included in the electrical schematics and so were left connecte was later determined that documentation did not exist confirming environmental qualification of the MOVs with space heaters energize I Corrective Action Taken and Results Achieved The following corrective actions have been taken: The space heaters for the affected motor-operated valves have been deenergize . The motor-operated valves in question have been evaluated to determine the impact of the space heaters having been energize The review determined that the energized heaters would not have significantly increased the temperature of the motors above normal ambient conditions so that, from a temperature standpoint, the qualification of the valve motors was not challenged. Documentation of this evaluation will be added to the environmental qualification package for the Et powered motor operators by July 7, 198 Corrective Action Taken to Prevent Recurrence Plant design has been reviewed to determine if this concern with space heaters has occurred elsewhere. No other instances have been found where space heaters are energized inappropriatel A1/049.NL2 |
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| During the review of SI System Vent Lineup 2 POP 02-SI-0002-16, two Train B valves were noted to be missing from the lineup. The two valves were the Test Vent Valves 2-SI-0138 and 2-S1-0101 *
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| The SI System Vent Lineup 2P0P02-SI-0002-16 listed Valve 2-SI-0231, which e s previously deleted. The valve was not shown on the system P&ID, neither was the valve listed in the system initial lineup. A review of documentation was perfomed to detemine if the valve was shown to be deleted when operations performed the SI system vent lineup. The licensee could not locate documentation to verify that Train B of the SI system was vented per 2 POP 02-SI-0002-16. However, Train B of the SI system was vented per 2 PSP 03-SI-0014, Revision 1, | |
| "ECCS Valve Checklist " on February 13, 1989.
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| During the inspection of the mechanical auxiliary building (MAB) in Unit 2, Boric Acid Tank Room 076 was visited. The NRC inspectors observed y local Sample Connection Valve 2-CV-0322 leaking excessively. This valve was slowly draining boric acid from Boric Acid Tank 2B onto the floor of the room. The Unit 2 shift supervisor was immediately notified. The licensee fully shut the valve and generated a problem repor The NRC inspectors observed control room operations, reviewed applicable
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| logs, and conducted discussions with control room operators. The NRC inspectors verified the operability of selected emergency systems, reviewed tag-out records and verified proper return to service of affected components, and ensured that maintenance requests had been initiated for equipment in need of maintenanc One apparent violation and no deviations were identified in this area of the inspectio . Monthly Maintenance Observations - Unit 1 (62703)
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| Portions of selected Unit 1 maintenance activities were observed to ascertain whether the activities were conducted in accordance with approved procedures. The activities included:
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| Maintenance Work Request (liWR) SY46861, Seismic Monitoring System
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| Preventive Maintenance (PM) IC-0-EM86007175, Revision 9A, Meteorological Monitoring System Inspection The NRC inspectors tried to determine through observations whether approved procedures were being used, replacement parts were properly certified, and housekeeping was being maintained. Specific items noted during the observation of PM IC-0-EM-86007175 included:
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| Both the Primary and Backup Meteorological (Met) towers had instruction manuals and drawings that were uncontrolled and out of date. Having manuals available for use by the technicians in remote locations, such as the Met towers, can be beneficial. However, having uncontrolled or out-of-date copies of manuals for troubleshooting or maintenance purposes may lead to problems. The manuals and drawings have since been recalled for updating or disposal by the license *
| | South Texas Project Electric Generating Station Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Response to Notice of Violation (498/8911-01: 499/8911-01) |
| A box inside the primary Met tower contained what appeared to be spare parts. The spare parts were inside zip-lock bags that provided some identification as to what the parts were, however, there were no material issue forms included in the box that identified the date or j source of issue. The spare parts have since been returned to the L Instrumentation and Control (I&C) shop for dispositionin An uncontrolled history file was being maintained at both Met tower The information that was gathered as part of the PM was being
| | VI, pate of Full Como11ance The spaca heaters identified above have been deenergized and do not represca,; g tor.L.inued' challenge to the environmental qualification of the motor operator'. The effects of the past operation of the space heaters has been determined to be within the boundaries of the existing environmental qualification of motor operators. Therefore, HL&P is in full compliance at this tim A1/049.NL2 |
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| transferred to copies of out-of-date data sheets. These data sheets were then being added to the history files. The history files have since been returned to the I&C shop for review to determine their usefulnes * The primary and backup Met tower electric generator batteries were observed to have standing water on top of them. The potential existed where the water could have shorted out the batteries. The batteries were cleaned by the licensee on the day of inspectio *
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| The primary Met tower was noted to be in need of cleanin Housekeeping was not being maintained in an acceptable manner. Loose paper, dirt, dead insects, and other items were noted throughout the room. Prior to the end of this inspection period, the room was cleaned by the license Observations noted during the review of MWR SY-46861 included:
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| Technicians were noted to be troubleshooting the circuitry of Seismic Monitor Channel Sensor XT0002A. Troubleshooting activities included removing the. sensor for testing, lifting leads for a wire check and meggering, and reterminating the lifted leads. All troubleshooting activities were performed using verbal instructions provided by the foreman of the task. A review of the MWR was performe Authorization to troubleshoot the circuitry was not a part of the MW Instructions on troubleshooting activitim were provided in OPGP03-ZM-0021, Revision 1, " Control of Configuration Changes During Maintenance or Troubleshooting." Section 6.2.1 of the procedure requires, in part, that troubleshooting is to be performed using approved work instructions and as part of an MWR. The technicians, following the instructions of their foreman, appeared to exceed the authorization allowed for troubleshooting per OPGP03-ZM-0021 without revising MWR SY-4686 TS 6.8.1 requires written procedures to be established, implemented, and maintained, including applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, " Quality Assurance Program Requirements (Operation)." Written procedures required per Appendix A of RG 1.33 included procedure adherence and performing maintenanc Contrary to the above, on April 27-28, 1989, technicians apparently violated TS 6.8.1 by performing maintenance activities that did not adhere to requirements established by 0PGP03-ZM-0021. Although the seismic monitoring system is considered nonsafety related, their operability is required by TS 3.3. Thisapparentviolation(498/8911-02;499/8911-02)ofTS6.8.1will not be cited because the criteria specified in Section V. A. of the i
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| enforcement policy were satisfied. Corrective actions taken by the licensee subsequent to the apparent violation included personnel training and perfonning a teview of current procedures to detemine and clarify the scope of troubleshooting activitie *
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| During the performance of MWR SY-46861, an inspection ot the Unit 1 tendon gallery was performed. Housekeeping was not being maintained, as indicated by grease on the floor of the tendon galler Approximately 2-3 gallons of grease was located in the center of the floor. A tendon in the tendon gallery was leaking grease significantly. The sheathing filler grease cap was leaking grease on Tendon V222. After the condition was reported to the licensee, a second tendon (V209) in Unit 2 was noted by the licensee to be leaking grease. Nonconformance reports were written for the two
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| tendons. The licensee advised that each unit has 96 vertical tendons and all will be inspected at least every 6 weeks for signs of additional leakage. Containment structural integrity is required by TS 3.6.1.6. The licensee stated that the leakage of grease from the two tendons did not affect the structural integrities of the two reactor containment building The ladder area leading to the Unit 1 tendon gallery was inadequately illuminated. The area from the top of the first ladder to the second ladder was observed not to be illuminated, and was considered to be an obvious safety hazard. The tendon gallery is an area of the plant that is not traversed by plant personnel on a regular basi One apparent violation and no deviations were identified in this area of the inspectio . Monthly Surveillance Observations - Units 1 and 2 (61726)
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| An inspection of Unit 1 licensee surveillance activities was performed to ascertain whether the surveillance of systems and components was being conducted in accordance with TS and other requirements. The following surveillance tests were cbserved and reviewed:
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| IPSP02-SI-0953, Revision 1, " Accumulator 1B Level Group 2 ACOT (L-0953)"
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| * IPSP02-SI-0963, Revision 1, " Accumulator IB Pressure Group 2 ACOT (P-0963)"
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| The NRC inspector verified that testing was performed using approved procedures, final test data was within acceptance criteria limits, and test equipment was within required calibration cycles. A technical review of the procedures was also performe During the review of IPSP02-SI-0963, Section 7.5 was noted to be misnumbered. Section 7.5 had two steps numbered as 7.5.3. Step 7. j l I L
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| l instructed the technician to go to Step 7.5.4 if a computer point was unavailable. Due to the misnumbered steps, the potential existed of referring a technician to, the wrong step (7.5.4). Verbatim compliance with S'.ep 7.5.2 would have sent the technician to the wrong ste Step 7.6.3 of IPSP02-SI-0953, instructed the technician to verify that an annunciator alarmed when a comparator tripped. The comparator was reset in the next step. Step 7.6.7 verified the same alarm energized when a second circuit was tripped. There were no steps between 7.6.3 and 7. that verified that the annunciator alarm cleared. The same procedure for Unit 2 (2 PSP 02-SI-0953) included Step 7.6.6, which verified that the alarm was clear. The same observation also applied to Procedure 1 PSP 02-SI-096 An inspection of Unit 2 licensee surveillance activities was performed to ascertain whether the surveillance of systems and components _ were being conducted in accordance with TS and other requirements. The following surveillance tests were observed and reviewed:
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| 2 PSP 02-SI-0931, Revision 0, "RWST Level Set 2 ACOT (L-0931)"
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| 2 PSP 02-SI-0952, Revision 0, " Accumulator 2B Level Group 4 ACOT (L-0952)"
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| During the review of 2 PSP 02-SI-0952, the procedure was compared to the same procedure for Unit 1 (1 PSP 02-SI-0952, Revision 1). Differences were noted between the two procedures. The differences inclutad:
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| The Unit 1 procedure additionally had Step 6.1 which referred the technician to TS action statements for LC0 requirements. The Unit 2 procedure did not have a similar ste The Unit 2 procedure had three additional steps in Section 7.6 to verify that an annunciator was clear before, during, and after testing. The Unit 1 procedure did not perform these step *
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| Steps 7.7.1 (remove all test equipment) and 7.7.3 (ensure annunciator deenergized) were double signoff steps for independent verification of actions in the Unit 1 procedure. The same steps in the Unit 2 procedure were single signoff steps, with no independent verification of the steps require Additionally, the NRC inspector noted the tenninal strips in the Unit 1 Relay Cabinet ZRR-012 had protective covers, but the terminal strips in the Unit 2 Relay Cabinet ZRR-010 did not have protective cover The terminal strips were noted to be nonsafety related, howeve In conclusion, testing was performed using approved procedures, final test data was within acceptance criteria limits, and test equipment was within required calibration cycles. None of the observations were considered
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| safety significant concerns. The discrepancies were referred to the 1
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| licensee for resolution. No violations or deviations were identified in this area of the inspectio )
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| 7. Monthly Maintenance Observations - Unit 2 (62703)
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| The NRC inspectors observed portions of selected Unit 2 maintenance activities to ascertain whether the activities were conducted in accordance with approved procedures. The activities included Work Request CH-78095, " Add Oil to Essential Chiller 218." The essential chillers provide cooling to selected safety-related equipment during upset and faulted condition The problem description on the work request was, " Essential Chiller 21B upper oil sightglass is empty when chiller is running, add oil as required." The work observed included postmaintenance testing of Chiller 21B following maintenance. The following items were noted during the inspection:
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| Procedure OPMP05-CH-0001, Revision 1. " York Chiller Inspection and Maintenance," Section 6.5.5, provided instructions on how to check the oil level with the chillers either operating or shut down. With low oil level (as written on Work Request CH-78095), Addendum 4 was required to be performed. Addendum 4 provided instructions to start the chiller (Step 1), install a jumper to energize a solenoid (Step 2), allow the solenoid to remain energized for approximately 5 days (Step 3), and monitor oil level every 4 hours (Step 4).
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| Step 3 was not completed in its entirety before Step 4 was performe The chiller did not run for 5 days prior to maintenance performing Step 4 and postmaintenance testing. Steps 3 and 4 of Addendum 4 should be adhered to or revised by the licensee to clarify how long the chiller is required to operate prior to performing oil level
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| . heck * Discrepancies were noted to exist between the essential chilled water (CH) system operating procedures, maintenance procedures, and the vendor manual with respect to proper chiller oil leve Step 8.1.1 of Operating Procedure 2 POP 02-CH-0001, Revision 1,
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| " Essential Chilled Water System," stated " Verify the operating oil level is above the top of the lower sight glass to the middle of the upper sight glass for (Chillers) 22A, 22B, and 22C. The oil level is visible in the sightglass for (Chillers) 2!A, 21B, and 21C. If oil level is out of range contact maintenance for correction."
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| Step 6.5.5.1 of OPMP05-CH-0001 stated " Verify operating oil level is from the top of the lower sightglass to the middle of the upper sightglass." Step 6.5.5.2 stated " Verify shutdown oil level to be at
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| least at the top of bottom sight glass to the middle of upper sight glass." Both steps applied to both sizes of essential chillers, the 300-ton units (22A-C) and the 150-ton units (21A-C).
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| The vendor manual for Chillers 21A-C indicates proper operating oil level is from the lower sight glass to the middle of the upper sight glas A vendor representative informed the NRC inspector that proper oil level for all chillers exists when oil is visible in the upper sight glass with the unit operating, and oil level can be reliably checked only during chiller operatio Discrepancies noted with the above statements included:
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| Step 8.1.1 of 2 POP 02-CH-0001 implied that Chillers 21A-C have only one sightglass to verify oil level, but the chillers actually have two sightglasses, an upper and lower on *
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| Vendor instructions were not located by the NRC inspector or licensee personnel for proper oil level for the "open drive" type chillers, 22A-C. The oil reservoir is physically different between the "open drive" and "hcrmetic" chillers. Vendor instructions were provided only for hermetic chiller Step 6.5.5.2 of OPMP05-CH-0001 indicated shutdown oil level should be no higher than the middle of the upper sight glass. Actual shutdown level will vary, depending on purge drum (removes noncondensable gasses from chiller) level at shutdown, length of shutdown and chiller temperature. Also, actual shutdown oil levels for the open drive chillers (22A-C) were noted to be above the top of the upper sightglass (disagrees with requirements of Step 6.5.5.2).
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| Additionally, (providedverballyStep)6.5. disagrees that oil level with be could only vendor instructions reliably checked during chiller operatio MWR CH-78095 was written to add oil to Chiller 218. Per wording of the vendor manual, the chiller had sufficient oil, therefore, the MWR was an unnecessary but conservative actio *
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| Step 8.1.1 of 2 POP 02-CH-0001 instructed the operator to verify operating oil le' vel of a chiller, but the chillers are not started until Step 8.1.8 of the procedur Step 8.1.1 should be revised to verify the oil level of a shutdown chiller is above a certain level, or Step 8.1.1 should be placed after Step 8. This subject area will be tracked as an open item (499/8911-03) until all procedures in question have been revised to agree on how to check essential chiller oil level, and operations personnel are trained on the i
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| proper way to check operating and shutdown oil levels.
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| No violations or deviations were identified in this area of the inspectio . Preparation for Refueling Observations - Unit 1 (60705)
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| The NRC inspectors observed the testing of a carbon arc cutting device and the generation of the basic requirements for a procedure to which it is qualified and used. The device was tested on a mockup of the bottom half shell of a steam generator; the shell included one primary loop nozzle and the manway cover and flang The purpose of the equipment is to extract a broken bolt / stud in the manway flange if that event' occurs during the first Unit I refueling outage. (The center of the bolt is cut out and the sides are collapsed.)
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| The overall unit encompasses: a fixture which can be bolted 'to the manway flange, a positioner which will align the cutting head to the bolt hole, a cooling unit, power control, and the graphite electrode cutting tool. The unit is operated by positioning the device in the hole with the broken bolt / stud, starting the cooling system (the system providns coolant to the electrode and washes away the residue), end energizing the power unit to the cutting electrode. When the cut has been made, the electrode is withdrawn and the resultant "shell" of the bolt can be collapsed inwardly and removed from the flange. Once set up, the operation can be performed remotely, thereby reducing or keeping personnel exposure to penetrating radiation to a minimum. The NRC inspectors did not have any concerns in the development of the proces No violations or deviations were identified in this area of the inspectio . Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1) on May 4,1989. The NRC inspectors summarized the scope and findings of the inspection. The licensee did not identify as proprietary any of the information provided to, or reviewed by, the NRC inspector .
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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F8821990-11-15015 November 1990 Ack Receipt of 901017 Response to Violations Noted in Insp Repts 50-498/90-28 & 50-499/90-28 IR 05000498/19900101990-11-0909 November 1990 Ack Receipt of 900711 & 1003 Ltrs Informing NRC of Corrective Measures for Weaknesses Noted in Insp Repts 50-498/90-10 & 50-499/90-10 ML20062F8911990-11-0707 November 1990 Advises of Postponement of Soviet Delegation Visit to Plant Site Due to Unavailability of Seats on Aeroflot. Representatives Will Try Again to Obtain Seats in 2 Wks.Nrc May Reschedule Visit to Plant If Representatives Successful ML20216J9651990-11-0606 November 1990 Concludes That Actions Proposed in Util Response Met Intent of Generic Ltr 88-17, Loss of Dhr ML20062E3841990-11-0606 November 1990 Advises That 900914 Proposed Rev to Exam Schedule for Class 1 Nozzles Complies W/Asme Section XI Code XI-1-86-74 ML20058E2941990-11-0202 November 1990 Forwards Summary of Staff Understanding of Current Status of Generic Safety Issues Which Remain Unimplemented IR 05000498/19900311990-11-0101 November 1990 Discusses Insp Repts 50-498/90-31 & 50-499/90-31 on 900912- 21 & Forwards Notice of Violation IR 05000498/19900051990-10-31031 October 1990 Ack Receipt of 901001 Request for Extension of Corrective Action Implementation Date for Violations Noted in Insp Repts 50-498/90-05 & 50-499/90-05.Commitment to Implement Corrective Actions Prior to Aug 1991,acceptable ML20058A5941990-10-18018 October 1990 Requests Addl Info Re Review of Probability Safety Assessment of Facility ML20059M7001990-09-28028 September 1990 Forwards Insp Repts 50-498/90-27 & 50-499/90-27 on 900813-17.No Violations or Deviations Noted ML20059N7721990-09-24024 September 1990 Forwards Safety Evaluation Accepting Util First 10-yr Interval Inservice Insp Program Plan ML20059K9321990-09-18018 September 1990 Forwards Insp Repts 50-498/90-28 & 50-499/90-28 on 900730- 0808 & Notice of Violation.Violation Re Mixed Bed Demineralizer of Particular Concern Because Potential for Inadvertent Reactivity Not Mitigated ML20059J9971990-09-13013 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered on 901010 IR 05000498/19890471990-08-31031 August 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-47 & 50-499/89-47.Review Will Be Documented in Insp Repts 50-498/90-30 & 50-499/90-30 ML20059F0921990-08-30030 August 1990 Forwards Request for Addl Info Re Fire Protection Modeling in Probability Safety Assessment.Answers to Questions Will Form Basis for 900919 Meeting in Rockville,Md ML20059D5861990-08-27027 August 1990 Confirms 900830 Mgt Meeting in Region IV Ofc to Discuss Scenario Exercise Weaknesses Identified During Apr 1990 Emergency Exercise at Plant ML20056B3971990-08-20020 August 1990 Forwards Partially Withheld Insp Repts 50-498/90-22 & 50-499/90-22 on 900604-08 & Notice of Violation ML20056B3191990-08-17017 August 1990 Forwards Insp Repts 50-498/90-24 & 50-499/90-24 on 900701-0801.No Violations or Deviations Noted ML20056A7791990-08-0808 August 1990 Discusses Licensee Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Justification for Differences in Program & Generic Ltr Should Be Incorporated Into Program Description ML20056A7751990-08-0707 August 1990 Forwards Request for Addl Info Based on Review of Probability Safety Assessment at Plant ML20056A7981990-08-0303 August 1990 Advises That 900122 Relief Requests Re Pump & Valve Inservice Test Plan Acceptable & That Stroke Time Criteria Need Not Be Documented in Plan Itself,If Included Elsewhere in Procedures.Any Revs to Plan Should Be Provided to NRC ML20056A7961990-08-0303 August 1990 Advises That Util Response to Generic Ltr 88-06 Re Implementation of Spds,Acceptable ML20055G8191990-07-19019 July 1990 Forwards Insp Repts 50-498/90-23 & 50-499/90-23 on 900601-30.No Violations or Deviations Noted IR 05000498/19900011990-07-19019 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01 ML20055G0771990-07-13013 July 1990 Advises That Most Portions of Rev 16 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable. Portions Noted in Encl That Decrease Effectiveness of Plan Should Be Resubmitted.Encl Withheld (Ref 10CFR73.21) ML20055F5831990-07-10010 July 1990 Advises That 900601 Rev 10 to Safeguards Contingency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20055F7431990-07-0505 July 1990 Advises That Util 900216 Response to Bulletin 89-003, Potential Loss of Required Shutdown During Refueling Operations, Acceptable ML20059M8401990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20248H5811989-10-0505 October 1989 Forwards Summary of 891003 Meeting in Region IV Ofc Re Activities Authorized by Licenses NPF-76 & NPF-80 ML20248H2151989-10-0505 October 1989 Forwards Insp Repts 50-498/89-31 & 50-499/89-31 on 890814-25.No Violations or Deviations Noted IR 05000498/19890171989-09-29029 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-17 & 50-499/89-17 ML20248C6901989-09-28028 September 1989 Forwards Insp Repts 50-498/89-35 & 50-499/89-35 on 890814-18 & Notice of Violation ML20248C6101989-09-27027 September 1989 Forwards Insp Repts 50-498/89-33 & 50-499/89-33 on 890821-25.Violations Noted,But No Citations Will Be Issued, Per NRC Policy ML20248C6731989-09-26026 September 1989 Forwards Insp Repts 50-498/89-30 & 50-499/89-30 on 890801-31.No Violations or Deviations Noted ML20247R3021989-09-22022 September 1989 Forwards Insp Repts 50-498/89-37 & 50-499/89-37 on 890911-15.Violations Noted.No Citation Issued Per Section V.A of NRC Enforcement Policy ML20248G9491989-09-21021 September 1989 Forwards Unexecuted Amend 6 to Indemnity Agreement B-108, Reflecting Increase in Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20248E6121989-09-21021 September 1989 Forwards Safety Evaluation Re Deletion of Dynamic Rod Drop Test,Static Rod Cluster Control Assembly (Rcca) Test & Rcca Below Bank Position Measurement Tests Based on Review of Util 890728 Submittal.Deletion Acceptable ML20247H5281989-09-12012 September 1989 Forwards Insp Repts 50-498/89-36 & 50-499/89-36 on 890821-25 & Notice of Violation ML20247K2001989-09-12012 September 1989 Advises That Rev 1 to Licensee Licensed Operator Requalification Program Meets 10CFR50.59 Requirements & Acceptable.Revised Rule Stated in Generic Ltr 87-07 Offered as Alternative to Submitting Program for Review ML20247D4521989-09-11011 September 1989 Forwards Insp Repts 50-498/89-25 & 50-499/89-25 on 890724-28 & 0807-11.No Violations or Deviations Noted. Independent Safety Engineering Group Appeared to Be Below Goal for Performing Direct Plant Observations ML20247B6891989-09-0101 September 1989 Forwards Summary of 890825 Meeting W/Util in Region IV Ofc Re Activities Authorized Under Licenses NPF-76 & NPF-80. Better Understanding of Util Operations,Refueling Outage & Mgt Programs Provided ML20246M9411989-08-31031 August 1989 Forwards Insp Repts 50-498/89-22 & 50-499/89-22 on 890710-14.No Violations or Deviations Noted ML20247A5621989-08-30030 August 1989 Forwards Summary of Region Iv/Senior Util Executive Meeting on 890818 at Univ of Texas.Agenda & List of Attendees Encl ML20246E9721989-08-25025 August 1989 Forwards Insp Repts 50-498/89-26 & 50-499/89-26 on 890718-20.No Violations or Deviations Noted ML20246A3271989-08-16016 August 1989 Forwards Insp Repts 50-498/89-28 & 50-499/89-28 on 890731-0804.No Violations or Deviations Noted ML20245L5451989-08-15015 August 1989 Forwards Insp Repts 50-498/89-17 & 50-499/89-17 on 890601-30 & Notice of Violation ML20245H3801989-08-11011 August 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/89-10 & 50-499/89-10 ML20245J5211989-08-10010 August 1989 Forwards Insp Repts 50-498/89-15 & 50-499/89-15 on 890607-30 & Notice of Violation.Actions Taken Re Previous Insp Findings Examined 1990-09-28
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses ML20210D9011999-07-23023 July 1999 Forwards Safety Evaluation Re Inservice Testing Plan Request for Relief RR-5 Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210C2111999-07-21021 July 1999 Forwards Insp Repts 50-498/99-13 & 50-499/99-13 on 990516-0626.Two Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209H9231999-07-16016 July 1999 Discusses South Texas Project,Units 1 & 2 Updated Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity. Staff Revised Info for Plant in Rvid & Being Released as Rvid Version 2 ML20207H6261999-07-0808 July 1999 Responds to Re 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546, Alternative Requirements for Qualification of VT-2 Exam Personnel,Section Xi,Division 1.Forwards SE ML20195J6731999-06-17017 June 1999 Responds to Re Request for Relief from ASME Code, Section Xi,Requirement to Perform VT-1 Visual Exam on Accessible Surfaces of RPV Flange Inserts (Bushings). Safety Evaluation Encl ML20195F7561999-06-10010 June 1999 Forwards Insp Repts 50-498/99-11 & 50-499/99-11 on 990404-0515 at South Texas Project Electric Generating Station,Units 1 & 2.No Violations Were Identified ML20207H0031999-06-0909 June 1999 Discusses 990419 Meeting in Region IV Ofc Re South Texas Project EP Program Status,Including Initiatives in EP Program,Future Revs to EP & Dept Performance Indicators. Meeting Attendance List & Licensee Presentation Encl ML20195G3241999-06-0909 June 1999 Ack Receipt of Re Changes to Plant Emergency Plan Change Notice 18-2.No Violations of 10CFR50.54(q) Were Identified ML20207D7371999-05-28028 May 1999 Discusses Re Process for Reclassification of non- Risk Significant Components.Forwards Concerns & Cautions for Consideration Based on Limited Review of Reclassification Process Overview That Was Provided IR 05000498/19980151999-05-28028 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/98-15 & 50-499/98-15.Corrective Actions Reviewed & Found to Be Responsive to Issues Raised ML20207E1961999-05-25025 May 1999 Forwards Insp Repts 50-498/99-09 & 50-499/99-09 on 990503-06.No Violations Noted.Primary Focus of Insp to Review Operational Status of Emergency Preparedness Program ML20207A8771999-05-25025 May 1999 Forwards RAI Re Licensee 960213 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Units 1 & 2.Response Requested within 120 Days from Date of Ltr IR 05000498/19990061999-05-12012 May 1999 Submits Corrected First Page of Cover Ltr Re Insp Repts 50-498/99-06 & 50-499/99-06 Conducted on 990221-0403.Subj Line Was Corrected ML20206S3201999-05-12012 May 1999 Forwards Corrected First Page of Cover Ltr,Which Forwarded Insp Repts 50-498/99-06 & 50-499/99-06,issued on 990505. Subj Line Indicated on NOV Was Incorrect ML20206N5481999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ra Gramm Will Be Section Chief for South Texas Project.Organization Chart Encl ML20206J4321999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206J4211999-05-0606 May 1999 Ack Receipt of in Response to & Insp Repts 50-498/99-04 & 50-499/99-04,confirming Commitments as Stated in 990225 Exit Meeting ML20206H6201999-05-0505 May 1999 Forwards Insp Repts 50-498/99-06 & 50-499/99-06 on 990221- 0403.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3811999-05-0505 May 1999 Responds to STP Nuclear Operating Co Which Provided Update to TS Bases Pages B 3/4 2-6.Revised TS Bases B 3/4 2-6 That NRC Staff Will Use to Update Copy of STP Bases Encl ML20206H2001999-05-0404 May 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation ML20206B6091999-04-22022 April 1999 Forwards Insp Repts 50-498/99-10 & 50-499/99-10 on 990405-09.No Violations Noted ML20206B3281999-04-22022 April 1999 Forwards Insp Repts 50-498/99-07 & 50-499/99-07 on 990405- 09.Insp Focused on Radiological Controls in Place During Unit Refueling Outage.Violations Identified Involving Failure to Follow Radiation Work Permit Instructions ML20205Q8151999-04-16016 April 1999 Forwards Request for Addl Info Re Proposed Amends on Operator Action for small-break-LOCA,dtd 980728.Response Requested within 45 Days of Ltr Date ML20205P5821999-04-15015 April 1999 Advises That Version of Application & Affidavit Dtd 990127, Executed by Ha Sepp,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended 1999-09-09
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JLI8IW i In Reply Refer To:
Dockets: 50-498/89-11 50-499/89-11
Houston Lighting & Power Company ATTN: J. H. Goldberg, Group Vic President, Nuclear P.O. Box 1700 Houston, Texas 77001 Gentlemen:
Thank you for your letter of June 16, 1989, in response to our letter and Notice of Violation dated June 7, 1989. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintaine
Sincerely, Original Signed D3
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James L. Milhoan, Director Division of Reactor Projects cc:
Houston Lighting & Power Company ATTN: M. A. McBurnett, Manager Operations Support Licensing P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: Gerald E. Vaughn, Vice President Nuclear Operations P.O. Box 289 Wadsworth, Texas 77483 RIV:DRP/Dh C:DRP/ :DRPw DMHunnicutt;df EJHoller' 4.JCa=fMn3LMAn- O!
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Houston Lighting & Power Company -2-Houston Lighting & Power Company ATTN: J. T. Westermeier, General Manager South Texas Project P.O. Box 289 Wadsworth, Texas 77483 Central Power & Light Company ATTN: R. L. Range /R. P. Verret P.O. Box 2121 Corpus Christi, Texas 78403 City of Austin Electric Utility ATTN: R. J. Miner, Chief Operating Officer (2 copies)
721 Barton Springs Road Austin, Texas 78704 ;
Newman & Holtzinger, ATTN: J. R. Newman, Esquire 1615 L Streat Washington, Houston Lighting & Power Company ATTN: S. L. Rosen P.O. Box 289 Wadsworth, Texas 77483 Houston Lighting & Power Company ATTN: R. W. Chewning, Chairman Nuclear Safety Review Board j P.O. Box 289 Wadsworth, Texas 77483 City Public Service Board ATTN: R. J. Costello/M. T. Hardt P.O. Box 1771 '
San Antonio, Texas 78296 i
Houston Lighting & Power Company ATTN: Licensing Representative- l Suite 610 Three Metro Center Bethesda, Maryland 20814 Houston Lighting & Power Company ATTN: Rufus S. Scott, Associate General Counsel P.O. Box 1700 Houston, Texas 77001 i
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Houston Lighting k Power P.O. Box 1700 Houston. Texas 77001 (713) 228 9211 June 16, 1989 ST-HL AE-3141 File No. G02.04 _ '
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U. S. Nuclear Regulatory Commission 3@
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Attention: Document Control Desk
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South Texas Project Electric Generating Station
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Units 1 & 2 Docket Nos. STN 50-498. STN 50-499 Resnonse to Notice of Violation (498/8911-01: 499/8911-01)
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Houston Lighting & Power Company has reviewed Notice of Violation (498/8911-01; 499/8911-01) dated June 7,1989, and submits the attached response pursuant to 10CPR2.20 If you should have any questions on this matter, please contact Mr. M. A. McBurnett at (512)972-853 /
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G. E. Vaughn Vice President Nuclear Operaticns CEV/PLV/eg Attachment: Response to Notice of Violation (498/8911-01; 499/8911-01)
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Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston I.ighting & Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 George Dick, Project Manager U. S. Nuclear Regulatory Commission INPO Washington, DC 20555 Records Center 1100 Circle 75 Parkway Jack E. Bess Atlanta, CA 30339-3064 Senior Resident Inspector - Unit I c/o U. S. Nuclear Regulatory Commission Dr. Joseph M. Hendrie P. O. Box 910 50 Be11 port Lane Bay City TX 77414 Be11 port, NY 11713 ~
J. I. Tapia Senior Resident Inspector - Unit 2 c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City, TX 77414 J. R. Newman, Esquire Newman & Holtzinger, P. L Street, N. Washington, DC 20036 R. L. Range /R. P. Verret Central Power & Light Company P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 Copies)
Chief Operating Officer City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 Revised 12/21/88 A1/049.NL2
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g Attachment ST HL- AE 3141 1 Page 1 of 3 South Texas Project Electric Generating Station Units 1 & 2 4 Docket Nos. STN 50-498, STN 50 499 Response to Notice of Violation (498/8911-01: 499/8911-01) )
1 Statement of Violation
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10CFR50.49, paragraph (f) requires that (environmental) qualification of each component m ~ust be based on testing or experience with identical equipment, or with similar equipment with a supporting analysis, to show that the equipment to be qualified is acceptabl Paragraph (k) of 10CFR50.49 states that equipment previously required by the Commission to be qualified to NUREG-0588, " Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment," -
need not be requalifie Paragraph 5(1) of NUREG-0588 states that the qualification documentation shall verify that each type of electrical equipment is qualified for its application and meets its specified performance requirements. The basis of qualification shall be explained to show the relationship of all facets of proof needed to support adequacy of the complete equipmen Data used to demonstrate the qualification of the equipment shall be pertinent to the application and organized in an auditablo for Contrary to the above, the equipment qualification file, which contained Wyle Laboratories Report No. 47664-05, " Assessment Report on Limitorque Operators For Use in South Texas Nuclear Power Plant," for eight auxiliary feedwater valves with space heaters installed and energized, did not support qualification. This was due to the failure to analyze all possible effects of energized space heaters used within the motor operator. No analyses were contained in the files to fully establish qualification for air temperature rises of cables, wires, splices, and components resulting from their proximity to the heater I Houston Lir_htine & Power Positior HL4R concurs that the cited violation occurred.
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South Texas Project Electric Generating Station Units 1 & 2 Docket Nos. STN 50-498, STN 50 499 Response to Notice of Viqlation (498/8911-01: 499/8911-01)
III. Reason for Violation The cause of this violation is failure of design personnel to recognize the need to disconnect the space heaters. This resulted from the fact that normally, heater elements are wired to a terminal strip on points separate from the wiring of the motors and the limit and torque switches. However, in the case of these DC-operated MOVs, the motor beater element leads were connected by the vendor to the same points on the terminal strip used in wiring the motor leads. Design personnel only evaluated the seismic qualification impact of the space heaters, ""
and did not consider the environmental impact of the heaters on operability of the valves. Consequently, the heater elements were It included in the electrical schematics and so were left connecte was later determined that documentation did not exist confirming environmental qualification of the MOVs with space heaters energize I Corrective Action Taken and Results Achieved The following corrective actions have been taken: The space heaters for the affected motor-operated valves have been deenergize . The motor-operated valves in question have been evaluated to determine the impact of the space heaters having been energize The review determined that the energized heaters would not have significantly increased the temperature of the motors above normal ambient conditions so that, from a temperature standpoint, the qualification of the valve motors was not challenged. Documentation of this evaluation will be added to the environmental qualification package for the Et powered motor operators by July 7, 198 Corrective Action Taken to Prevent Recurrence Plant design has been reviewed to determine if this concern with space heaters has occurred elsewhere. No other instances have been found where space heaters are energized inappropriatel A1/049.NL2
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South Texas Project Electric Generating Station Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Response to Notice of Violation (498/8911-01: 499/8911-01)
VI, pate of Full Como11ance The spaca heaters identified above have been deenergized and do not represca,; g tor.L.inued' challenge to the environmental qualification of the motor operator'. The effects of the past operation of the space heaters has been determined to be within the boundaries of the existing environmental qualification of motor operators. Therefore, HL&P is in full compliance at this tim A1/049.NL2
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