ML19322A891
| ML19322A891 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/12/1973 |
| From: | Jape F, Murphy C, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19322A888 | List: |
| References | |
| 50-269-73-02, 50-269-73-2, NUDOCS 7911270646 | |
| Download: ML19322A891 (18) | |
See also: IR 05000269/1973002
Text
{{#Wiki_filter:-- - . - . . . . . - - ( 3 V. ,- #* %, UNITED STATES " ( Yg ATOMIC ENERGY COMMISSION l .,e< - 1 DIREC % RATE OF REGULATCRY CPERATICNS '
neciou n - su:ve eis s , ',[I'4 rt s O' f am pene t act sracer. sent .cs, , , , , , , , , , , , , , , , , , , , , , , ATLANTA,GEoRG#a 30 3C 3 10 Inspection Peport No. 50-269/73-2 - Licensee: Duke Power Company Power Building 422 South Church Street Otarlotte, North Carolina 28201 Facility Name: Oconee Unit 1 Docket No.: 50-269 License No. : DPR-38 Category: B2 Location: Oconee County, South Carolina Type of License: B&W, PWR, 2568 MW(t) - Type of Inspection: Special, Announced Dates of Inspection: February 3-4, and 7-16, 1973 - Dates of Previous Inspection: December 30, 1972, January 17-19, 30 - February 2, 5, and 26, 1973 Principal Inspector: R. F. Warnick, Reactor Inspector Facilities Test and Startup Branch Accorpanying Inspectors: F. Jape, P4 actor Inspector Facilities Test and Startup Branch . M. S. Kidd, Reactor Inspector Facilities Test and Startup Branch , Principal Inspector: 7 [_, 4.% u ch 3hC/'S R. F. Warnick, Reactor Inspector Date Facilities Test and Startup Branch ._/[J 3 Reviewed By:, // / C. E. Murphyg A tingfief, Facilities Test and bats Startup Branen .
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4. . ( BO Rpt. No. 50-269/73-2 -2- '. . - . ' St204ARY OF FINDINGS I. Enforcement Action A. Violations 1. Design Changes The operations organi=ation had no documented instructions or procedures to implement the requirements of the fourth paragraph of Criterion III, " Design Control," pertaining to the reviews, approvals, and control of design changes in- cluding field changes. This appears to be contrary to Criterion V of Appendix B to - 10 CFR 50 which requires that activities affecting quality to
be prescribed by documented instructions. (See Details I, ' paragraph 2.) B. Safety Items l 1 None II. Licensee Action on Previously Identified Enforcement Matters A. Violations . None B. Safety Items None III. New U.asolved Items None , IV. Status of Previously Peported Unresolved Items 70-9/16a Axial Power Imbalance (See FO Inspection Report No. 50-269/70-9, Su=marv - Outstanding ltea 16 a . ) - Region II has received a copy of procedure TP-800/24, "Pcwer Imbalance Detector Correlation," and has reviewed it. Comments will be discussed with the licensee on a subsequent inspection. 1 i
_ -. . - , _ _ . . . . . .- . . _ _ _ _ _ . - _ . . ( 'RO Rpt. No. 50'-269/73-2 -3- ' f .I' . 71-7/1 Thin Walled Valves (Also see RO Inspection Recort No. 50-269/71-5, De tails C . 3. ) The licensee's report on the wall thicknesses of valves within the reactor coolant system pressure boundary has been received by Pagion II and remaining unresolved items identified. The Region is awaiting action by DPC. 71-10/1 Flow:9.eter Error Analysie and Tests RO is awaiting infomation and action from DPC concerning this item. 72-8/l Calibration of Licuid Flow Meter on Waste Discharge Line The calibration of the 0-50 gpm meter on the liquid waste discharge line has been completed. This item is closed. (See Details I, paragraph 3.) 72-8/4 Verification of In-Plant Air Flows ( The question of air flow from waste handling areas to clean areas still exists. . 72-8/15 Verification of Hood Air Flows The verification of hood air flows has not yet been shcwn
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to be satisfactory. 72-C/16 Filter Test of Hydrogen Purge System The test has been completed. This item is open pending evaluation of test results. 73-1/1 Development of Administrative Procedures - ' The licensee has issued nine administrative procedures in answer to concents and questions RO had previously raised on Operating and Maintenance Procedures. This item is closed. (See Details II, paragraph 5.) 73-1/2 Resolution of Test Deficiencies This item remains active. (See Details I, paragraph 6, and Details II, paragraph 3.) , . m ,
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r . ~ , , t RO Rpt. No. 50-269/73-2 -4- ' . _ _ . 73-1/3 Preoperational Tests to be Comoleted Prior to Initial Fuel Loading _ These previously identified tests have been completed. This item is closed. (See Details II, paragraph 2.) 73-1/4 Preoperaltonal Tests to be Completed Prior to Initial Criticality This item remains active since all tests have not yet been completed. 73-1/5 glysis and Approval of Preoperational Test Resulte Required Before Initial Fuel Loading The results from all tests required prior to initial - fuel loading have been analyzed and accepted by the licensee. This item is closed. (See Details II, paragraph 2.) 73-1/6 Analysis and Approval of Preoperational Test Results Required Prior to Initial Criticality This item remains active. The reviews have-not yet been cc cpleted. 73-1/7 Emergency Operating Procedures There are seven emergency conditions for which procedures will be written and approved prior to initial criticality and one for which a procedure will be written within three months. 73-1/0 Alarm Procedures Alarm procedures for all safety related systems have been w ritten. These will be approved prior to initial criticality.' V. Design Changes A. Chemical Addition During Steam Generator Wet Layug - , ' A modification has been made to the piping outside the reactor building on the secondary side of the steam generators so that chemicals can be mixed and added during wet layup of the steam generators. (See Details I, paragraph 4.) . .s,. .
_ . , .. .. _ _ . _ __ _- - -- - - -- . e i RO Rpt. No. 50-269/73-2 -5- . . .B . Reactor B'uildinc Purge Valves ' The limitorque valve operators for the two 48-inch butterfly valves PR-V1 and PR-V6, the reactor building purge inlet and outlet valves, have been replaced to provide operators that are rated for high radiation service, as required by the FSAR. (See Details I, paragraph 5.) - VI. Unusual Occurrences A. Control Rod Drive (CRD) Undervoltage Device A CRD undervoltage device failed to trip a DC breaker when voltage was removed from the coil. In addition, two under- voltage coils have failed eithin the past six months because of overheating. (See attached Advance Inspection Information dated, February 27, 1973.) VII. Other Significant Findines A. Initial Fuel Loading Operating License DPR-38 was issued to DPC for Oconee Unit 1 on February 6,1973. The inspector * verified that preoperational test requirements prerequisite to . fuel loading were completed and the inspectors witnessed portions of the initial fuel loading. The first assembly was placed into the reactor at 11:15 a.m. on February 9 and the final assembly.was placed into the reactor at 5 :19 a.m. on February 16, 1973. After mechanical difficulties were resolved, fuel leading proceeded smoothly and during the last two days of fuel loading, the loading rate was approximately three assemblies per hour. The initial fuel loading was conducted in a safe and orderly manner and in accordance with applicable procedures , the FSAR, Technical Specifications , and license requirements. (See Details I, paragraphs 8-14, and Details II, paragraphs 2-5.) . VIII. Management Interview At the conclusion of the inspection, a Management Interview was held on February 16, 1973, with the following DPC representatives present: J. E. Smith - Plant Superintendent M. D. McIntosh - Operating Engineer R. M. Koehler - Technical Support Engineer L. E. Summerlin - Staff Engineer T. L. Cotton - Jr. Engineer
u_. _ - _ . ~ _ _ ,-___ ~_ = -- - m_ f 4 t . R 1 -6- M , pt. No. 50 269/73-2 - , . The following itees were discussed: A. Enforcement Action The status of enforcement action, as described in the summary of findings , was discussed with the Plant Superintendent by telephone following the inspection. B. Previously Reported Unresolved Items The status of previously reported unresolved items, as described in the summary of findings, was discussed with the Plant Superintendent by telephone following the inspection. C. Review and Evaluation of Test Results The inspector discussed four completed tests , which had been reviewed and approved, where identified deficiencies were not completely resolved. The Plant Superintendent confirmed that necessary follewup action would be taken. (See Details I, paragraph 6.) D. Emergency Procedures The licensee confirmed that an emergency procedure to cover the malfunction of a pressurizer relief valve would be written. .. (See Details I, paragraph 7.) E. Control Rod Drive (CRD) Undervoltage Device The licensee confirmed that a report would be submitted to the AEC pursuant to the requirements of 10 CFR 50.55(e) , concerning the failure of a CRD undervoltage trip device to trip a DC breaker when voltage was removed from the coil, and the failure of two undervoltage trip devi ce coils because of overheating. (See Advance Inspection Info.mation Memorandum dated, February 27, N' 1973, which is attached.) F. Audit of Log Books The inspector stated that he had reviewed the Shift Supervisors Log, Duty Supervisors Log and the Active Electrical Jumper and Bypass Log. There were no questions or comments on the first two logs, but the Electrical Jumper and Bypass Icg appeared to contain records of jumpers and bypasses that no longer are needed. The licensee 's representative. stated that this log i will be re-tewed and any jumper or typass no longer needed
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will be removed. (See Details II, paragraph 4.) .
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. RO Ept. No. 50-269/73-2 I-l ~ ' . - DETAILS I Prepared By: [[[ 2A,+ucI" 3/#/7S R. F. Warnick, Reactor D6te' Inspector, Facilities Test and Startup Branch Dates of Inspection: February 3-4, 7-14, and 16, 1973 Prepared By:[[4 M f/ 7f e _ M. S. Kidd/ Reactor Date Inspector, Facilities Test and Startup Branch Dates af Inspection: February 7-10, 1973 Reviewed By: etM / t7 2 3 D&te , C. E. Murphy , Actingpief Facilities Test and Startup Branch 1. Individuals Contacted a. Duke Power Company (DPC) . J. E. Smith - Plant Superintendent J. W. Hampton - Assistant Plant Euperintendent M. 3. McIntosh - Operating Engineer R. M. Koehler - Technical Support Engineer L. E. Schmid - Assistant Operating Engineer G. W. Cage - Assistant Operating Engineer L. E. Sumnerlin - Staff Engineer C. L. Thames - Health Physics Supervisor O. S. Bradham - Instrument and Control Engineer D. G. Beam - Project Manager, Construction D. L. Freeze - Principal Field Engineer Sin Se:ior Eeactor Operators , Six Reactor Operators b. Babcock and Wilcox Coreany (B&W) J. S. Dossett - Lead Engineer, Mechanical Equipment ' K. L. Hladek - Senior Fuels Development Engineer
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_ __ _ _ 1 n . _ _ _ _ . .__ _ _ _ . _ _ -_ _ _ _ - __m-___ . ,* '%,' RO Rpt. No. 50-269/73-2 I-2 t . 2. Design changes .Appenuix B to 10 CFR 50 states that " Activities affecting quality " shall be prescribed by documented instructions . Contrary to .. this requirement, the inspector found that the Operations organization had no documented instructions or procedures to implement the requirements of the fourth paragraph of Criterion III of Appendix B to 10 CFR 50. The fourth paragraph of Criterion III states " Design , changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and be approved by the organization that performed the original design unless the applicant designates another responsible organization." This information was discussed with the Plant Superintendent by telephone on March 12, 1973. During the management interview, the Plant Superintendent agreed to prepare administrative instructions to cover design changes. Calibration of Liquid Flow Meter on Rad Waste Discharge Lined./ 3. A new flow meter was installed and was calibrated. This previously reported item is now resolved.
4. Steam Generator Wet Layup , A modification has been made to the piping outside of the reactor building on the secondary side of the steam generators so that chemicals can be added to either steam generator during wet layup. The mixing tank, pump, piping, and valve arrangement in the East Penetration Room were inspected and verified to be as shown on approved drawing No. 0-439A, Revision 17. No further inspection effort is planned. 5. Reactor Building Purge valves The limitorque motor valve operators on the reactor building - purge supply and exhaust valves (48-inch butterfly valves manu- factured by Henry Pratt)' were replaced with limitorque motor valve operators which meet the design requirements stated in paragraph 6.1.2.12 of DPC's FSAR. Originally only certain parts of each valve operator were to be changed, but economically it ~~ was easier to replace the entire operator of each valve. . / k 1/ See RO Inspection Report No. 50-269/73-1, Details V, paragraph 3. - .
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i - . Tne' old valve operators did not have Melamine as the nonmetallic material for the switch base on the torque switch and the geared limit switch, cast iron limit switch component cover, pressure relief valve, or Jiton seals. The inspector determined that the design change installation was controlled by an approved field installation procedure (FIP No. 293) . No further inspection effort is planned. 6. Preoperational Test Procedures The inspector reviewed certain precperational test procedures to ensure they had been completed, the test data evaluated, and the results approved. Also to see if the test purposes had been accomplished and all test deficiencies identified and resolved. The inspector has no further questions at this time concerning the following tests: TP-200/3C, " Reactor Coolant System Hy' dro." TP-200/5C, " Reactor Coolant Pump Initial Operation" " Auxiliary Drains and Liquid Waste- Disposal Functional TP-230/6, Test" TP-253/3, " Plant Hydrogen System and Reactor B~uilding Hydrogen Purge Unit Instrument Calicration" IP-301/3K, " Source Range Response Check with Check Source" ~ IP-301/30, " Reactor Protective System and Nuclear Instrumentat!i n" IP-330/2D, "Contro.' Rod Drive System Patching Scheme and Functional Cable and Patching Test" IP/361/lA, " Radiation Indicating Alarm System Calibration and Functional Test" i TP-600/18, " Reactor Protective System Functional Test" . TP-600/22, "Degasification Test" Although the following tests had been completed and approved, tt e inspector identified needed actions which DPC agreed to followup , Followup action will be documented under unresolved item on. 73-1/2, Resolution of Test Deficiencies. . TP-361/2, " Evacuation Alarm System Test" DPC agreed to install a speaker in room 505. TP-600/5, " Reactor Coolant System Chemistry" DPC agreed to followup on test comments submitted by B&W. ( . _
- - , ..__.m. - .- s _. - - - - - - % . (% , , RO itpt. No. 50-269/73-2 I-4 . - . TP-600/6, " Steam Generator Chemistry Test" DPC agreed to followup on test coments submitted by B&W. TP-600/21, " Hydrogen Addition Test" The hydrogen regulators 'on the letdown storage tank will be -modified to regulate at 35 psig, instead of the present 20 psig. The inspector verified that the following tests had been completed and the results approved, but the inspector did not review the test results: TP-200/1, " Reactor Iriternals Vent Valve Inspection" TP-200/12, " Reactor Coolant Pump Flow Test" TP-200/34, " Reactor Vessel and Internals Flow Induced Vibration Test" TP-200/37, " Reactor Coolant Loop Cooldown Verification" TP-210/8, " Trace Heating Functional Test" TP-230/2C, " Liquid Waste Disposal System Hydro and Leak Test" TP-230/5, " Soluble Poison Control Test" . TP-275/12, " Emergency Feedwater Pump Initial Operation Test" , TP-600/8, " Component Cooling Water Operational-Test" , TP-600/23, " Emergency Operation of NSS" TP-600/27, " Center CRD Venting" TP-800/22, " Thermal Measurement for 1B Steam Generator Fluids" No nurbor, " Final Fuel Assembly Inspection and Spent Fuel Pool Cleaning" 7. Emergency Procedure s The problem of malfunctioning safety and relief valves at operating reacters was discussed. The licensee agreed to write an emergency procedure to cover malfuncticn of the pressurizer safety relief or power oparated valves. Malfunction of the main steam relief valves , is already covered by a procedure. 8. Initial Fuel Loading The inspection of February 3-4, 1973, was conducted to determine - that preoperational test requirements, prerequisites to initial fuel loading, were completed and that the results of certain tests had been reviewed, evaluated, and approved by the licensee. In addition, the inspector reviewed .and evaluated the results of certain tests to evaluate adherence to requirements specified in the test procedures, the FSAR, and other applicable documents. % 1
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'The inspection of February 7-16, 1973, was conducted to determine that the prerequisites for initial fuel loading were completed; to verify that personnel staffing requirements had been fulfilled; to witness the initial fuel loading; to review the collection and interpretation of data; to evaluate adherence to requirements of the Technical Specifications, FSAR, procedures, and other applicable documents; and to conduct a management interview of the inspection
activities. The first fuel assembly was placed in the reactor at 11:15 a.m. on February 9,1973. The final assembly was loaded into the reactor vessel at 5:19 a.m. on February 16, 1973. After the first fuel assembly was placed in the core, mechanical difficulties were experienced with the fuel handling equipment. After these were resolved, fuel loading proceeded smoothly _ J during the last two days of fuel loading, the licensee loaded approximately three assemblies per hour. The fuel loading was conducted as described in procedure OP-1502/4, " Initial Fuel Icading." The incectors observed that the enclosures to the procedure were properly film out and reviewed by supervisory personnel, that the boron samples were within procedural limits , that nuclear instrumentation w'as on-scale and responding, and that inverse multiplication plots were being accurately calculated and plotted. The initial fuel loading was conducted:in a safe and orderly manner and in accordance with applicable procedures , FSAR, and Technical
Specifications requirements. 9. Fuel Loading Problems After the first fuel assembly was placed in the reactor, mechanical problems with the fuel handling equ'.pment were experienced. These prcble=s slcwed the progress of the operation during the first four days of the fuel loading. The inspectors noted that when fuel , handling or equipment problems were encountered, the personnel in charge pursued a conservat'ive course. The inspectors also observed that the fuel handling crews folicwed appropriate operating procedures. One of the problems resulted in an assembly being returned to the manufacturer for examination and repair. Details of this event are as fcilows. The second fuel assembly tra-aferred into the reactor building , - could only be lifted approximately four feet in the eart upender _, (the west upender was out of service initially) before the main
__ -_ , .. _- . . . _ _ .- - , -- . ( l ' t . 50-269/73-2 I-6 Rpt. , fueling bridge hoist overload limit was reached. The assembly (No.1C67) was transferred back to the spent fuel pool (SFP) where it was removed frem the water and visually examined. There wcs evidence of some distortion on the second intemediate spacer grid 130-40 mils) and there appeared to be some bcwing and twisting. The assembly was sent to B&W at Lynchburg for examination and repair. B&W confimed the bowing (50 mils in six foot length) but found no twist. Before resuming' core loading, the east upender was checked out using a dummy fuel assembly without encountering any problems or identifying the cause of the problem. When fuel loading was . resumed, no other trouble was experienced with the east upender. Tne fuel assembly was repaired by B&W and returned to the site in time to be loaded in its original preassigned reactor location. Nothing unusual was noted when the assembly was loaded into the reactor. 10. Verification of Fuel Loading Prerecuisites 1 The inspectors verified that the following prerequisites or initial conditions were acccmolished prior to the start of initial fuel loading: Area radiation monitors operable.* a. b. Peactor building evacuation alarm operable, One low pressure injection pump and cooler in operation.* c. d. The core had been indexed using the fueling bridge main hoist and a dummy fuel assembly. i , The spent fuel cooling system was operable.* e. , f. The spent fuel pool (SFP) and transfer canal water levels were at the normal operating level of the SFP* , and borated to greater than 1900 ppm. The reactor coolant water temperature was between 50*F and 140*F.* g. h. Both doors on the emergency hatch were closed.* 1. The personnel hatch doors were closed and the hatch was in operation.* y j. The equipment hatch cover was bolted in place.*
.. . _ - -.. _ -. --. _ - - . __ . - s ' . ! . . ,3 k _' RO Rpt. No. 50-269/73-2 I-7 , All personnel entering and leaving the containment building were k. signing in and out.* Only individuals approved by the plant superintendent or the 1. senior reactor operator on duty were allowed into the reactor building *. Personnel numbers, qualifications and assignments met technical m. specification and procedural requirements.* r Direct comunications were established between the control n. room, the refueling personnel in'the reactor building, and refueling personnel in the spent fuel pool area.* Two incore flux monitors had been calibrated re.*ponse checked, o. and were in service. The readouts were in the reactor building . and the count rate of one was audible in the reactor building.* Two out-of-core flux monitors had been calibrated, response p. checked, and were in service. The readouts were in the control room and and the count rate of one was audible in the control ' room.* , Stations were set up in the control room and in the reactor q. building to record neutron count rates and plot; 1/M data.* . Both isolation valves in lines containing automatic containment r. isolation valves were operable of at least one was closed. A tag board was located in the control mom to folicw the s. movements and location of each fuel assembly.* Required radiation work permit (FWP) was approved and posted i t. > at the step off pad area of the spent fuel pool and the reactor tuilding.* The spent fuel pool and transfer canal areas were clean.* ~ u. Provisions were in force to prevent foreign objects from being v. introduced into the spent fuel pool, the transfer canal, or the reactor vessel.* Health physics 'and chemistry monitoring personnel were assigned . w. to each shift. The reactor vessel and internals were clean. x. , f ' ( , Personally witnessed in the field by RO:II inspectors.
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_._.u_.. - - we. . - -, _--- ' . . .( RO.Rpt. No. . 50-269/73-2 I-8 ' . . . 11., Fuel Loading Procedures The inspectors verified that tiie latest revisions to the following procedures, or parts thereof, had been completed prior to, or were in use during fuel loading. OP-1103/18, Control and Accountability
OP-1502/04, Initial Fuel Loading OP-1503/01, Preparation for Refueling OP-1506/01, Fuel and Component Handling 12. Logbooks The inspector reviewed certain logbooks to identify any conditions which might indicate that the station was not ready for fuel to be loaded into the reacy.cer. No deficiencies or unresolved items were noted. The following logbooks were reviewed: Beactor Operation Log - December 30,1972 through February 8, 1973 Out of Normal Logbook - All entries I Unusual Condition Reports - No.17,18, and 19 13. DPC Audits Both station and corporate headquarters personnel were observed conducting audits of the initial fuel loading. Check lists and audit procedures were being used. 14. Reactor Vessel and Internals The inspector examined the reactor vessel and the reactor internals, and then reviewed the documentatien of the cleaning of the reactor vessel and the internals. The results were ccmpared with requirements of applicable procedures and the FSAR. ; She results were audited - by station quality assurance . personnel. No deficiencies were noted by station personnel or the inspector. 15. Barton D/P Cells In response to the inspectors inquiry, the Instrument and Control Engineer stated that the nuclear steam supplier had not made him aware of problems being experienced with Bhrton D/P cells, Models .f 368,384, and 386.
!h The inspector was informed that there are no model 384 or 386 - t D/P cells at Oconee; however, there are four model 368 units l- each measuring the D/P across the No.1 seal of a reactor coolant { pump. , r & . -- , . - , , .- - , - - , y y , ,- -
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_ _ _. . ; . , _ _ - . - () . - , RO'Rpt. No. 50-269/73-2 I-9 , - , The licensee does not plan to replace the four units at the present time, but they will maintain surveillance of them. 16. Barksdale Pressure Switches ' In resp;nse to the inspectors inquiry, DPC indicated there were no Model B2T-A12SS pressure switches installed at Oconee 1. The Instrument and Control Engineer indicated that earlier in Oconee construction they had four Barksdale pressure switches of a different model number in non-safety related systems. These were replaced because they did not meet the manufacturer's specifications on dead band (trip-reset) . l . % @ . O A , - e - - < - ,
. _ _ _ _ _ _ _ - _ - - - _ _ _ . . - . . . . - . . . _ - -. _ . _ _ _ ,_ .- ~ - . .: - ~ - -- - _ . ,, . . ['*n . ' BO'Rpt. No. 50-269/73-2 II-l - ~ DETAILS II Prepared By: AM N F. Jape, Reactof Inspector Date Facilities Test and Startup Branch Dates of Inspection: February 8-11, 1973 and '
February 14-16, 1973 Reviewed By: C .J 2 3 'C. E. Murphy, 3ctinjcr Chief Date Facilities Test ancr Startup Branch 1.* Individuals contacted J. E. Smith - Plant Superintendent M. D. McIntosh - Operating Engineer R. M. Koehler - Technical Support Engineer L. E. Summerlin - Staff Engineer 4 W. .A. Brown - Assistant Chemist L. E. Schmid - Assistant Operating Engineer G. W. Cage - Assistant Operating Engineer - 2. Preoperational Test Status . The status of all preoperational tests was reviewed and all tests previously identified _1_/ as required prior to fuel loading were completed and the test results have been analysed and accepted by DPC. The tests were conducted and the results analyzed as prescribed by DN's Administrative Policy Manual for Nuclear Stations. The inspecter had no question or comment on these procedures and un- resolved items 73-1/3 and 73-1/5 are now clcsed. . 3. Resolution of Test Deficiencies During a previous inspgetion three test procedures were identified as having a deficiencyd. The status of these three tests was reviewed - by the inspector and is presented below. . . 1/ See RO Inspection Report No. 50-269/73-1, Details II, paragraph 2(B)1 and 2. 2_/ See RO Inspection Report No. 50-269/73-1, Details II, paragraph 2( A) . ' l 1 .-
__ _ _ _ - _ _ _ _ _ - - -_ _ __- -- __ . : _ - --- - ,_ . . -- ' BD kpt. No. 50-269/73-2 II-2 . . -a . TP 600/27 Center CRD Venting The 0-rings have been replaced. There are no further questions on this test. b. TP 210/8 Trace Heati.ng Functional Test . The test results have been analyzed and found acceptable by DPC. The inspector has no further questions on this test. c. TP 361/2 Evacuation Alarm System Test There were two plant areas where the evacuation signal was not audible. In the Decon area, a speaker was installed, tested and found acceptable by DPC. In the second area, Room 505, a sign was installed on the door stating that the shift supervisor was to be notified whenever entry to this room was necessary. The inspector consnented that the sign does not appear to comply with the audibility condition of the acceptance require- l ment. The licensee's representative agreeded to install a speaker l in this room. With this con'.mitrent the inspector has no further questions on this test. 4. ~ Audit of Loc Bocks The inspector made an audit of the Shi'ft Supervisor's log, Duty Supervisor's log and the Active Electrical Jumper and Bypass log. The findings are presented below. Shift surerviscr's Log - The records reviewed covered the period frem February 2,1973, to February 12 1973. All entries in the . . logbook were as described in Duke Pcwer Company's Administrative Policy Manual for Nuclear Stations ( APM/NS) , Section 3.1.6, Operating _ Records and were in agreement with Crl etion XVII, " Quality Assurance Records" of Appendix B to 10 CFR 50. The inspector had no questions on this record. Duty Supervisor's Log - The record reviewed covered the period from February 7,1973, to February 14, 1973. All entries in the logbook were written in ink, and were legible. This record was in agreement with Criterion XVII, " Quality Assurance Records" of Appendix B to 10 CFR 50. The inspector had no ques >tions on this record. . ?-W' -f
. . _ . . _ _ . - - - w ~. - - - . - . . = . . . . - > - y Rpt..No. 50-269/73-2 II-3 Active Electrical Jumper and Bypass Log . The record reviewed covered the period from May 30, 1972., to 14, 1973. The log was maintained as described in February MP/1400/20, " Electrical Interlock and Circuit Bypass Procedure." The inspector questioned the need for the jumpers identified on The licensee's representative indicated that pages 33, 68 and 87. a complete review of all active jumpers and lifted leads would be made and those no longer needed would be restored to proper circuit It was further stated that future audits of this arrangement. record by DPC would include a review of the applicability of each jumper and lifted lead. 5. Development of Administrative Procedures In response to IO's connents and questions _./ on Operating and l Maintenance procedures, DPC has issued Administrative Procedures. The final, approved issued of the Administrative Procedures were reviewed by the inspector and there are no further questions on .this matter. l . . 1 l ,
) i 1 - s 1/ See PO Inspection Report No. 50-269/72-11, Details II, paragraphs 3 and 4. . % > }}