ML20210A970

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Discusses Allegation of Fuel Onsite.No License for Fuel & No Fuel Onsite.Resident Inspector Indicated That Dummy Fuel Assembly Onsite Used in Preoperationally Testing Fuel Handling Equipment
ML20210A970
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/03/1984
From: Westerman T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20197F755 List:
References
FOIA-85-59 NUDOCS 8601270254
Download: ML20210A970 (36)
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Text

{{#Wiki_filter:I p**?"'5%, UNITED STATES y NUCLEAR REGULATORY COMMISSION 7! 'I REoloN IV S 811 RYAN PLAZA oRIVE. SufTE 1000 ARUNGToN. TEXAS 78011 MEMORANDUM FOR: File FROM: T. F. Westerman, Enforcement Officer, Region IV

SUBJECT:

ALLEGATION OF F'UEL ON-SITE There was no license for fuel and there has been no fuel on site. The resident inspecter indicated that a dummy fuel assembly (containing no fuel) was on site and had been used in preoperationally testing the fuel handling equipment. Na further action is being taken by the Reactor Project Section. This information was previously contained in a handwritten memo to file that I wrote. This memo is to serve as a formal backup.

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T. F. Westerman Enforcement Officer ,. '] D ~/ A A1-L l / 9601270254 851212 PDR FOIA PDR G AR DEB S-59 F0lA-85-59 6 Itf

i 4 A 't Allegation No. ALLEGATION REVIEW

SUBJECT:

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ATTACliMENT A CP-SAP-16 g5 k,2 -',- ) Revision 6 .a TEST DEFICIENCY REPORT Page 8 of 8 ystem Name: 7Iv,,, / w76y/mv S Page / of 6 ( h W omponent Tag No: Safeth Non-Safety t Startup System No.:YI NTest Instruction / Procedure No.- /-[,9-f/7//-5-NM DESCRIPTION OF DEFICIENCY: T/d6 h /O/v/// 6 APA A s %h uW /7]AM/ '74/E./?(C' Z D 5.r>'8 2 821/M/A ~ / &?.A f &4Gr2i

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sr-8323s TEXAS UTILITIES GENERATING COMPANY ggf0 OFFICE MEMORA NDUM QNLN To M. R_ MeBav ( ~ 1 Glen Rose. Texas. A Sub s TDR 908 Please evaluate the subject TDR and provide the appropriate corrective action. Notify TUCCO Startup of your findings at your earliest convenience. Dick Camp REC /jg cc: J. T. Merritt P. E. Olson J. H. Owen L

CPP #12,147 TEXAS UTILITIES SERVICES INC. FORINFO ONLY OFFICE MEMOR ANDUM To R M wo cien no... Texas Ma v 19. 1983 subject COMANCHE PEAK STEAM ELECTRIC STATION TDR-908 'l l 5 Attached is a copy of TDR-908 with disposition as shown for your record. M. R. McBay i Engineerin nager T3t'd MRM:J J:CKMjGWB:KFM:ery . ( Attachment cc: ADDRESSEE (0) P. Oken (1) R. P. Baker (1) C . -;.:}j, BRJ s1699 ..Og F :).-.,. l,.

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AT* ACCENT A VOR IN CP-SAP-16 0$d Revision 6 TEST DEFICIE'CY REP T Page 8 of 8 System Na=e: y/I,veNw// s 7a d DR No.:_ h8 ( ( Co=ponent Tag No: Page / of 6 SafetFq ] Non-Safety 'Startup System No.:YI N !J Test Instruction / Procedure No.: l-88 f/ S*-86 DESCRIPTION OF DEFICIENCY: T/J6 N/pev/j/2 App p g a %W /?78%/ '7%45".A&~E5si?.dd2 -BP)/M/j0 _l A. Y8t$5m M / /Je j~/z& dP ~6ts 0N wS }g'j'~~~dy ed. & 8, bete 2iotz wt=11s /-TM/45, /-TA-rsM /_7f s.e 5,:> .3.02A /P/vm f6S 94 57Lon kwadce L%mosnnedh = /

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NMlW ^l! f/n/PR / ' REQUIRED RETEST: Initiated By: I-ME Date: -[- Engineering Evaluation of Deficiency Required: $ Yes ]No f& W ELif, & & y 7,,g Reference Docu=ents for Engineering Evaluation:s .;'f2 r Corrective Action / Retest Approved By: - Date: Corrective Action Completed: Lead Startup Engineer Date: System Test Engineer bk Retest Satisfactorily Completed: Date: System Test Engineer Scrap Verified By: Date: TUCCO QA Startup/ Turnover Surveillance Supv. Distribution: Original to Log TUSI Engineering Manager . w e.,w. Initiating STE TUCCO QA Startup/ Turnover Sem'a411="*a .M2 - 2

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w-TEXAS UTILITIES SERVICES INC. {

r. o. sox im. ctt.v nose. Texas noa CPPA #29,988 09, May 2,1983 R. E. Ballard Gibbs & Hill, Inc.

393 Seventh Avenue New York, N. Y. 10001 COMANCHE PEAK STEAM ELECTRIC STATION MINUTES OF MEETING REF: TWX #14,357

Dear f.r. Ballard:

Attached are minutes of meeting on HVAC temperatures and calculations up-date held at CPSES on April 20-21, 1983 If you have any questions or comments, contact K. Mcdonald at extension 517. ( Very truly yours, $4 $ M. R. McBa Engineer 4 Manager .G MRM:J J:C :G'J8:KFM:ery l Atischment cc: ARMS ADDRESSEE P. Olsen - TUGC0 SU D. Woodlan - TUGC0 Licensing J. T. Merritt, Jr. - TUGC0 SU E. Nicolaysen - G & H L -f#9 -.w M .t.2 .25

950 Attachment To CpFA #29,988 50 page ; ef 3 ( DATE: April 20,1953 ATTENDEES: E. Nicolaysen - G & H K. Mcdonald - CPPE P. Olsen - TUGC0 Start-Up B. Kaulfus - TUGC0 Start-Up J. Owen - TUGC0 Start-Up '~~ AGENDA ITEM 1: TDR-908 Containment Temperatures During the performance of Pre-op test 1-CP-PT-45-06, temperatures in various areas of the Containment were discovered to be above the maximum acceptable temperature. Further investigation showed that the temperature of air being supplied to the areas was above that required for adequate cooling. The temperature dtfference across the coils; however, was within design limits indicating that the coils were operating at design capacity. A. Neutron Detector llell (NDW) Cooling System ~ Three return ducts exhausting air from the NDW were carrying air at a temperature approximately 10" above the 135'F maximum. The remaining five exhaust ducts were well under the maximum. The air flows in all ducts were within design tolerance. ~ ~ E. Nicolaysen suggested that the three hot ducts were probably exhausting ( air from areas near reactor vessell where insulation was either damaged or loose. Since it is not feasible to inspect this insulation (due to inaccessibility) the following actions were suggested to TUGC0 Start-Up: 1. Reduce chilled water temperature at the chillers serving these coils to 55'F from the current 65'F design. 2. Increase the total air flow in the NDW cooling system by increasing the fan blade pitch. 3. Re-balance the NDW supply and return duct air flows as necessary to briig the return duct air temperature to within acceptable limits. 4. F.ecord all pertinent air flow and temperature data so that the appropriate design change documents can be issued. B. RPV Supports The temperature of air being supplied around the RPV supports was 10", above the 90'F specified by Westinghouse. It was concluded that reducing the chilled water temperature (previously described) should correct this problem. C. Pressurizer Room In the pressurizer room the temperatures at various levels indicated stratification of air. The temperature at elevation 885' was very near the b 120*F design temperature. At elevation 905' the temperature was over 130'F. A field inspection by the attendees resulted in the following conclusions: M e- 'm..

90 g#* Attac.. ment To CPFA !29,9ss Page 2 of 3 C. Pressurizer Room (Continued) . ~. 1. Insulation on the pressurizer vessell has several open joints and Joose latches which are allowing more heat to transfer to the room than accounted for in the cooling design. 2. The cooling air being supplied in the lower two thirds of the ro'om is all gravitating downward in the room and out the access doorways instead of convecting out the ventilation opening near the top of the room. 3. A new supply duct needs to be installed to take air from the CRCS ring duct and discharge into the top of the pressurizer room. The air presently being supplied to the room would then be reduced to compensate for the additional air discharged above. CPPE will initiate this design by DCA. AGENDA ITEM 2: Control Room Air And Temperature Balance The problems with achieving design air flows in the control room air conditioning - system supply plenum was discussed. The four units were designed,to be identical; but, train A units operate at higher air output than train B units. Further, the air flow in the 4 main supply trunks varies depending on which train of ( units is operating. The following was concluded: 1. The cooling coils, fans, etc. should be thorougnly cleaned and new filters installed before any further balancing is attempted. 2. The system should be balanced with train 'B' operating and all air flow i, data recorded. The train ' A' operating air flows should then be recorded. I 3. The above data will be reviewed by CPPE and G & H against the heat load calculations for the control room. Further action will be determined in this review. i AGENDA ITEM 3: Results Of HVAC Load Calculations - Update The updated non-safety HVAC load calculations were presented to CPPE. E. Nicolaysen stated that they reflected all the electrical and equipment loads which have been added since the original calculations were performed. Due to the new electrical loads there are some areas of the plant where maximum! temperature will exceed the 10a*F normal design during periods when outdoor temperature exceeds the 102*F normal design maximum for the area. The average anual temperature however, is well within design limits. Further discussion on the subject was deferred until April 21 when TUS! licensing personnel are in attendance. L ~ ...g., m. ,..%.+,.

. ~- r FOR Igo, Attachment To CPPA !29,933 ,, ;,,,, 3 ON1-( DATE: April 21,1983 ATTENDEES: E. Nicolaysen - G & H P. Olsen - TUGC0 Start-Up J. Isgro - G & H J. Owen - TUGC0 Start-Up K. Mcdonald - CPPE B. Kaulfus - TUGC0 Start-Up D. Woodlan - TUSI Licensing ~ AGENDA ITEM 1: Yearly Average Temperature - vs - Maximum Temperature The profile of yearly outdoor temoeratures based on U. S. Weather Bureau data for Ft. Worth and four year site study by Dames and Moore was presented. Also the results of calculations for plant temperatures in various areas based on different outdoor temperatures was presented. It was shown that the temperature excursions above 104'F were calculated to occurr during a maximum of 73 hours per year with the norm being 30 hours per year or less. The average annual temperature is less than 80*F. Based on the above, E. Nicolaysen suggested that the appropriate tables in the FSAR be revised to show this information. Don Woodlan stated that this would be acceptable. The table will have columes showing 1.) Extreme maximum temperature, 2.) Normal maximum temperature, and 3.) Yearly average temperature for each of the plant areas. When questioned about accident (LOCA) temperatures, E. Nicolaysen stated that the 122'F maximums still hcid for accident condition, becuase.the safety related cooling systems are designed with sufficient margin to maintain this temperature (, or less. G & H will prepare the necessary FSAR table revisions. AGENDA ITEM 2: Effect Of Item i On Electrical Equipment Environmental Qualification Both Joe 1sgro and Don Woodlan stated that this should have no effect on equipment qualification because all safety related equipment at CPSES is qualified for 122'F. A yearly average tenperature of less than 80'F would not be detrimental to this qualification. L d 2.f.:..; a.

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3* 2323-M1-0555 8 Appg,Ic g,g uschsqc::c=E; 2323-M1-0556 REv. 8 A. a 8. c!: AILS PROBLEtt: Durinc hot functional testino the recm te-carature in the upper level of the pressurizer compartment exceeded the desian limits. SOLUTI0ti: Provide additional ductwork for the udder level of the pressurizer compartment and revise existino ductwork as shown on pacas 2 thru 5. JUSTIFICAT!0ft: Redistribution of airflow will provide more effective coolinc of the cc-nartmant, Overall detien a i r#1 mr to the pressurizer compartment will not chance. 9 A _1 1,. O C RECEIVFD 4. - untream m:ICr: h1AY 161993 TOR-908 DOCUMFNT rnMTont p.,nj not 5. APPcC'7AI. SIC;74IGES: GWB:KFM !Lfi:ch 5-13-83 A. CRIG {A. M/l / /7 CATE [ d[ B. CE3IGI PJ:7" CT"* 73 CAIZ / l 6. vc::ra Fx:Deh"AI. RECUI:Ut YES NO X 7. 5"lA!.".ArD DISSIEU"!O!! AmS (Crigir.al) (1) K.F. Mcdonald (FME) (1) tra itF.'1 11-40 Cua.11ty Dx;ir.eerirn (1) M.L. flees (FME) (1) Acun. Eev 7 M ti for Crig. Design (1) Westingh m -Sits 811 '...h,,E:..

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\\ k., TUQ-1747 TEXAS UTILITIES GENT.RATLNG COMPANY OFFICE MEMOR ANDUM To J. T. Merritt Glen IL=e, Texas August 1, 1983 Subject Cmanche Peak Steam Electric Station .c SR-83-183 The attached form documents a deficiency recently verbally reported to the NRC. Please assign an engineer to evaluate this deficiency working directly with the undersigned to resolve this problem. We need to jointly determine by August 19, 1983, if this deficiency is formally reportable under 10CFR50.55 (e). Thank you for your cooperation. DAW Y da!bt.,, ,p ". G. Tolson h T GC0 Site CA Supervisor RGT/bil Attachment cca D. N. Chapman B. C. Scott C. T. Brandt G. R. Purdy M. R. McBay J. D. Hicks F0lA-85-59 mni

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DEFICIDICT RE7IDI REPCRf GtR M I. IDDrf1FICATICN , Design M C:nstruction Procurunent A.

Description:

- /,g e # Date Ident. 5-45 Date Distr. aMdMM-- B. Basis -@s II. EVAIDLTICM Yes !b Dnknown A. Deficiency identified in construction p:ccess [ ) B. Deficiency violaters technical specifications X C. Deficiency requires fe%r testing / evaluation T D. Deficiency generic on other plants X. E. Deficiency w rrants extensive rework Y III. PRELIMINARY CDICLDSICH Yes !b' Potentially Deficiency W J21e { Iv. - w Identified By: NME CIGNI7.ATICH d E/E d m ann W 0YM Y Nr-4D Exmm e<W / Name Orgarf12ation IMefcyzsV# M 4~

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h f S,*N W g f 44.ob.<Mv'y w&s/&4=^- x#sr/4 %A vI. - 72 h3 w aar VII. Disi - A CRIGINAL J ILE cc: m Site OA Supervisor Ihgineering & Construction Manager W " % /kfeno. W c7 &

,s During Startup testing for system 45-02, high temperatures were exoerienced in the annulus between the reactor vessel insulation and shield wall; soecifically, in the reactor vessel succort and neutron detector well areas. The failure to meet the acceptance criteria was reoorted by Test Deficiency Reports (TDR) TDR's 908 and 1221. Efforts to correct the high temocrature conditions during HFT were not successful. Therefore, a complete evaluation was initiated. Examination of test data indicates that more heat is being removed by the Cooling System than was originally anticipated (550 to 600,000 BTU /Hr vs. 250,000 BTU /Hr). An inspection of the area between the reactor vessel insulation and the cavity wall has been made. Three problems were found: 1. A significant ouantity of construction material was found in the annulus. 2. A channel iron supporting the vessel insulation was found to extend into the air flow space. 3. The minimum clearance between the legs of the channel f ron. supporting the insulation and the anproximately 7/8" at azimuth 180, cavity wall varied frgm to 1/8" or less at 0. The construction material has beeg removed from annulus (except for two g small lumps of concrete, one at 0 azimuth and one at about 270 azimuth). Calculations by G&H show that the air flow restriction caused by the channel fron can be overcome by lowering the chilled water temoerature and increasing air flow provided distribution around the vessel is imoroved. Sufficient cooling capacity exists for ooeration of Unit 1; OEI-227 is in process to provide cooling capacity for Unit 2. The insulation supplier (Transco) has informed Westinghouse that acproxi-mately 3/4" of the 1-7/8" channel iron leg can be removed. Transco has reviewed their analysis to confirm. Westinghouse Gibbs & Hill and the site are looking at what tooling is available to cut the channel iron (May cut 1" holes on 1-1/2" centers). Agreement has been reached on the cuantity of heat removed by the system (aporoximately 550 to 600,000 BTU /Hr). We have been unable to resolve the difference between the design heat load and the actual heat load. m h.

s Even though our evaluation is continuing, we feel with the infomation i gathered oresently, sufficient concern exists to reoort this item as a potentially reoortable condition. On comnletion of our evaluation, a reoort will be submitted orovidino final results. 4 E i 4

una s.a a suna as.u wn av _ .. v4wuu my, t To: Madsen/Itunnicut ASAP DATE: 7 / 29 / n1_ Datst TACILITY ll0TIF ICl.1 le il ITEM OR EVEllT REC 10llALACT1tl ILY REPORTS IIUST IllCLUDE SPEI.CilES (SEE POLICY CUIDE H0. B-26, REV.1), PA0 llEETINGS, OTitER IHPORTANT ETIllGS (IH REGI0li 0FFICE), Al;D A LISTIllG OF IMPORTANT VISITORS (INCLUDING APPLICABLE IIRC PERSON,,]{J!L), E DACK OF PACE FOR ADDITIO:rAI. EPACE*. ' Construction Verbal To SRIC POTENTIAL 50.55(e) Item: (Tracking Item Ref;CP-83-18) followup in accordance MC-2512/2513 Comanche PeakSES The licensee reported that it has been detennined DN 50-445 by calculation that the reactor vessel cavity cooling system must absorb more heat by a factor of approxi-mately two that the co61tng system was designed'to 8 handle. The. initial discoverly of excessively high temperatures in the cavity was during the hot functional testing. Some remedial measures to improve air flow have been taken but the cause of the excess heat generation has not been found. The licensee is continuing to. investigate this matte'r and will file a thirty day report. t . EASE Il0TE: STATUS OF UtRISUA1. SPECTAL TilSPECTIONS OR IINESTTf ATT0HS ARE TO'DE,Jt:Ct.1:aFP, III TUP. DAILY RE70!'*'3 EVERY TilURSDAY. BRANCll SICHATUI'.E ~ .}}

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