ML20210R883
| ML20210R883 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/25/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20210R875 | List: |
| References | |
| FOIA-86-293 5211-86-2076, NUDOCS 8605200097 | |
| Download: ML20210R883 (16) | |
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GPU Nuclear Corporation Nuclear
=e rs:r8o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber:
April 25,1986 5211-86-2076 Dr. Thomas E. Murley Region I, Regional Administrator U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 THI-l EQ Meeting Minutes This letter is to document the meeting between GPU Nuclear and the NRC on April 18,1986 at TMI to review environmental qualification.
Environmental Qualification discussion items were identified in both the NRC PAT inspection of March,1986, and NRC's letter of April 15, 1986.
Additionally, certain follow on actions and their status are described. The presentation material used during the April 18 meeting is provided as an attachment.
The April 18 meeting reviewed environmental qualification (EQ) of generic EQ items as well as briefly reviewed the development of the Environmental Qualification Master List for TMI. The interest in generic envirormiental qualification followed from the NRC PAT inspection. The more general reverification of EQ common items, i.e., cable, splices, tenninal blocks and connectors, together with findings and actions are more fully described below:
Electrical Cable The qualification program for cable at TMI-l consisted of a review of procurement records preceding 1980 and a review of procurement, installation and walkdown records for modifications and replacements since 1980. The reverification program completed and discussed at the April 18 meeting consisted of a review of the original work plus the tracing of cable identified on cable pull slips (for each of the specific EQ components) back to the original purchase orders. The reverification process confirmed the finding of the HRC PAT which identified a cable type not previously included on the EQ Master List. This cable, Kerite cable with fire retardant (FR) insulation, was immediately determined to be environmentally qualified for THI, and the qualification file for Kerite FR cable is complete and signed 8605200097 860512 PDR FOIA WEISSB6-293 PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation JA
5211-86-2076 April 25, 1986 i
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off.
It is speculated that the engineer at the time did not recognize from the purchase order that Kerite high temperature (HT) cable with an FR jacket was, from a qualification standpoint, different from Kerite FR. This error is judged to be one of human perfomance.
The reverification program of the post 1980 installations also identified a type BIW cable, used on the high range Reactor Building sump level transmitters (not required for accident mitigation but for Reg. Guide 1.97), that did not have a qualification file. The cable 1
is qualified, and a qualification file was completed and signed off.
In reviewing terminal block installations, more fully described below, short links (approximately five (5) feet) of unidentified cable were found internal to the Reactor Building air handling units. Since the qualification status of these short links of cable could not be determined in the available time frame, they were replaced with qualified cable and splices for two (2) of the 4
three (3) units prior to restart of the plant. All three have now been replaced. We have no reason to believe similar internally run component cables exist at TMI-1 based on re-verification activities, including inspections, since finding the cable in the Air Handling Units.
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Splices The splice verification program consisted of a review of procurement and installation records.
In the Reactor Building, Raychem splices are used in penetrations, teminal boxes and motors for EQ components.
In the Intermediate Building, splices are used for high voltage motors (Kerite SKV) and replacements for some terminal blocks (Raychem).
In the Auxiliary Building, in which the harsh environment is radiation only, splices are used
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for high voltage motors (Kerite SKV) and more recently, for some low voltage motors (3M). Splices were reverified as being properly identified and all i
have approved qualification files.
l Terminal Blocks
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The baseline EQ program for teminal blocks in boxes consisted of a review of i
available procurement records and sampling walkdowns to establish EQ
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identification. With'in the Reactor Building, the walkdowns consisted of a 100% review and confirmed that terminal blocks had all been replaced by 4
i Raychem splices.
A Within the Intemediate Building, where the harsh environnent is steam,100%
of the terminal blocks were field verified.
In the Auxiliary Building, in i
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which the harsh environnent is only radiation,13 of 32 teminal blocks were yisually inspected which provides a reasonable degree of confidence. The J
reverification walkdowns confirmed the presence of States, Stanwick and GE type blocks. The States terminal blocks models NT and ZWM are both qualified by a single test report. The Stanwick terminal blocks models DG and SLS are both qualified by a single test report and are composed of the same basic i
insulating materials.
Stanwick and States terminal blocks are virtually visually identical.
Qualification information on Stanwick blocks was available and compiled but was not included in the current qualification files. This file has now been reactivated.
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5211-86-2076 April 25, 1986 At the time of the April 18 meeting, we had not been able to confirm the GE series of blocks since they do not carry any readily visible identification.
Subsequent to the meeting, we removed from the plant an unused GE block and identified a mold number, which has now been traced back through GE confirming that the GE blocks are of the EB-5 and 6 type. The visual appearance of GE EB-5 and 6 blocks are the same. GE has informed us that blocks EB-5 and 6 are made of similar organic insulating material (phenolics) as that of the EB-25's and CR-1518 for which GPUN has a qualification file. The GE block file is being further augmented by additional records from the manufacturer.
We have also, since April 18, expanded the visual inspection of blocks in the Auxiliary Building to 31 of 32 (1 terminal block is inaccessible) and have confimed the reverification findings.
Connectors The baseline emironmental qualification of connectors indicated only Conax connectors were used as a common item. These connectors, from an emironnental qualification sense, provide only a moisture seal.
In the Reactor and Intemediate Buildings, all EQ instruments requiring moisture seals had Conax connectors as detemined by walkdowns or installation records. Conax connectors are not required in the Auxiliary Building, which is a harsh emironment for radiation only.
The verification effort confirms the methodology and results of the baseline program.
GPU Nuclear provided a discussion on the development of the TMI-l Master List for specific components including components required for accident mitigation, interactions and Reg. Guide 1.97.
Also discussed was how changes were made to the Master List, which has undergone two revisions since December,1984, and in fact, is maintained as a living document.
The reverification of EQ common items, while identifying four specific anomalies which were immediately qualified or replaced, provides confidence in the qualification status for those items.
Sincerely, H'. D. Hu ill Director, TMI-l HDH/LH/CWS cc:
R. Conte S. Ebneter W. Kane J. Thoma Attachments 0566A
GPUN/NRC EETING TMI-l EQUIPENT QUALIFICATION APRIL 18,1986 I.
INTRODUCTION / AGENDA R.F. WILSON II.
EQSTATUSELECTRICALCABLES J.F.MANCINELi' 1
A.
PAT FINDING B.
IDENTIFIGTION 0F EQ GBLE 1.
BASELINE 2.
REVERIFICATION (SINCE PAT FINDING)
C.
WHAT HAS BEEN DETERMINED III.
EQ CATEGORIES J.F.MANCINEI A.
SPECIFIC ITEMS B.
GEERIC ITEMS
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IV.
RESPONSETONRCAPRIL15, LETTER A.
HOW MASTER LIST WAS ESTABLISHED L.C.LANESE B.
GENERIC ITEMS J.F.MANCIN ETHODS USED FOR QUALIFICATION (0RIGINALANDREVERIFICATION)
C.
RESULTS OF REVERIFICATION PROCESS J. F. :'ANCINEI
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II. EQ STATUS - ELECTRICAL CABLES i
PAT FINDING REVIEW 0F EFV-2 A/B REVEALED CABLE NOT ON THE TMI-1 EQ MASTER LIST.
CABLE WAS IDENTIFIED AS KERITE FR.
4 GPUN READILY DETERMINED CABLE WAS ACCEPTABLE BECAUSE GPUN HAD AN OYSTER CREEK FILE, THAT ENVELOPED TMI-l ENVIRONMENT.
QUALIFICATION FILE FOR KERITE FR IS COMPLETE.
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IDENTIFICATION OF EQ CABLE TWO PHASE BASELINE CABLE IDENTIFICATION
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PHASE I - REVIES ORIGINAL PLANT PROCUREMENT RECORDS POWER & CONTROL CABLE - IDENTIFIED KERITE, HT INSULATION MISSED KERITE FR INSULATION INSTRUMENT CABLE - IDENTIFIED CONTINENTAL (ANACONDA),
SILICONE RUBBER INSULATION PHASE II - UTILIZE PROCUREMENT a INSTALLATION RECORDS FOR' RESTART MODIFICATIONS WITH PROCEDURAL CONTROLS 9
FOR FUTURE MODIFICATIONS, TO IDENTIFY THE BALANCE OF CABLES 4
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RESULTS OF BASELINE PROGRAM FOR CABLES THE FOLLOWING CABLE TYPES WERE IDENTIFIED AND QUALIFIED KERITE - HT CONTINENTAL - SILICONE RUBBER, FR, FEP BIW - EPR/CSPE SAMUEL MOORE - EPDM ROCKBESTOS - XLPE i
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REVERIFICATION EFFORT FOR CABLES FOLLOWING PAT FINDING, REVERIFICATION EFFORT WAS PERFORMED USING PROCUREMENT a INSTALLATION RECORDS PHASE I SCOPE OF EFFORT 17I SPECIFIC COMPONENTS
- s 700 CIRCUITS RESULT THE KERITE FR CABLE (PAT FINDING) WAS THE ONLY TYPE CABLE NOT PREVIOUSLY IDENTIFIED DURING PHASE I PHASE II SCOPE OF EFFORT 114 SPECIFIC COMPONENTS 450 CIRCUITS RESULT ALL CABLE WAS PROPERLY IDENTIFIED DURING PHASE II, ONE CABLE (BTW SILICONE RUBBER) WAS NOT ADDRESSED DURING 4
THE QUALIFICATION PROCESS AND HAS SINCE BEEN DEMONSTRATED TO BE ACCEPTABLE TO REACTOR BUILDING HIGH LEVEL TRANSMITTERS (R.G. 1.97)
FIELD VERIFICATION EFFORT FOR CABLE SCOPE OF EFFORT EIGHT EQ SPECIFIC COMPONENTS TEN CIRCUITS RESULTS CABLES WERE UNIDENTIFIABLE FROM PHYSICAL INSPECTION EXPOSED LENGTHS VARIED FROM 1 TO 6 FEET IN LENGTH BLACK RUBBER TYPE JACKET, NO IDENTIFYING MARKING COLOR CODED SINGLE CONDUCTORS, NO IDENTIFYING MARKINGS e
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CONCLUSIONS FOR CABLE IDENTIFICATION REVERIFICATION EFFORT REINFORCED THE ORIGINAL METHODOLOGY PHASE I UNIDENTIFIED CABLE RESULTED FROM ISOLATED ERROR & WAS NOT PROGRAMMATIC PHASE II LABLE HAD BEEN PROPERLY IDENTIFIED QUALIFICATION FILE BEING FINALIZED FOR BIW SILICON RUBBER I
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III EQ CATEGORIES A.
SPECIFIC ITEMS EQ MASTER LIST IDENTIFIES THE VAST MAJORITY OF COMPONENTS BY UNIQUE TAG NUMBER (285 SPECIFIC ITEMS)
B.
GENERIC OR COMMON ITEMS ELECTRICAL CABLE (7 TYPES)
TERMINAL BLOCKS (3 TYPES)
SPLICES (4 TYPES)
EQUIPMENT SEALS (2 TYPES) i
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TMI-I EQ MASTER LIST IDENTIFICATION I.
DEFINED FIVE (5) BASIC SAFETY FUNCTIONS 2.
DEFINED DESIGN BASIS ACCIDENTS - ESTABLISHING EQUIPMENT EQ 3.
DEFINED ASSUMPTIONS 4.
DEFINED EQ ENVELOPE FOR ACCIDENTS 5.
DEVELOPMENT OF EQ MASTER LIST A.
SYSTEMS REQUIRED FOR MITIGATION B.
IDENTIFIED R.G. I.97 INSTRUMENTATION C.
INTERACTICN ITEMS 1
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IDENTIFICATION OF E0 TERMINAL BLOCKS BASELINE FROM REVIEW 0F INITIAL WALKDOWN SAMPLING STATES GENERAL ELECTRIC STANWICK RAYCHEM SPLICES REPLACED TERMINAL BLOCKS IN REACTOR BUILDING REVERIFICATION SINCE PAT FINDING REACTOR BUILDING (LOCA)
ALL 8 TERMINAL B0XES CONTAINED RAYCHEM SPLICES AS CONFIRMED BY EQ ENGINEER INTERMEDIATE BUILDING (HELB)
WALKDOWN OF ALL SEVEN (7) TERMINAL BOXES VERIFIED STATES, GE OR RAYCHEM AUXILIARY BUILDING (RADIATION ONLY)
WALKDOWN OF 13 0F 32 TERMINAL BOXES VERIFIED STATES, GE AND STANWICK CONCLUSION CONFIRMED IDENTIFICATION METHODOLOGY IS SOUND ALL IDENTIFIED TERMINAL BLOCKS ARE QUALIFIED w
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IDENTIFICATION OF SPLICES BASELINE METHOD SAMPLING OF MODIFICATION DOCUMENTS WALKDOWN SAMPLE INFORMATION RAYCHEM KERITE SKY 3M REVERIFICATION REACTOR BUILDING (LOCA) 15 PENETRATIONS
'RAYCHEM - QUALIFIED 8 TERMINAL BOXES - RAYCHEM - QUALIFIED 3 LO VOLTAGE FAN MOTORS - RAYCHEM - QUALIFIED VERIFIED BY WALKDOWN OR INSTALLATION DOCUMENTATION AUXILIARY BUILDING (RADIATION ONLY) 7 HI VOLTAGE PUMP MOTORS - SKV KERITE - QUALIFIED 6 L0 YOLTAGE PUMP MOTORS - 3M SPLICE - QUALIFIED YERIFIED BY INSTALLATION DOCUMENTATION INTERMEDIATE BUILDING (HELB)
I TERMINAL B0X - RAYCHEM - QUALIFIED 2 III VOLTAGE PUMP MOTORS - SKY KERITE - QUALIFIED VERIFIED BY WALKDOWN OR INSTALLATION DOCUMENTATION CONCLUSION METHODOLOGY IS SOUND SPLICES IDENTIFIED ARE QUALIFIED e
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IDENTIFICATION OF EQUIPMENT SEALS BASELINE REVIEW BY SAMPLE WALKDOWNS REVERIFICATION CONAX CONNECTORS (SEALS)
REACTOR BUILDING (LOCA) 38 COMPONENTS REQUIRING CONNECTORS CONAX CONNECTORS - QUALIFIED VERIFIED BY WALKDOWN BASELINE OR DOCUMENTATION AUXILIARY BUILDING (RAD ONLY)
NO EQ COMPONENTS REQUIRE CONNECTORS INTERMEDIATE BUILDING (HELB)
FOUR COMPONENTS REQUIRING CONNECTORS CONAX CONNECTORS - QUALIFIED VERIFIED BASELINE WALKDOWN CONCLUSION METHODOLOGY IS SOUND EQUIPMENT SEALS IDENTIFIED ARE QUALIFIED w
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z, RESULTS OF REVERIFICATION EFFORT OF GENERIC ITEMS METHODOLOGY FOR IDENTIFICATION IS SOUND BY THE REVERIFICATION EFFORT PAT FINDING RESULTED FROM AN ISOLATED ERROR GEN 5RICITEMSIDENTIFIEDAREQUALIFIED i
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KING OF PRUSSIA. PENNSYLV ANI A 19406
.- !4'.E Docket No. 50-289 GPU Nuclear Corporation ATTN:
Mr. H. D. Hukill Director, TMI-1 P. O. Box 480 Middletown, Pennsylvania 17057 Gentlemen:
Sub.iect: TM1-1 Equipment Qualification Meeting inis 'ietter is to confirn t e d anced meeting to be held at 10:00 a.m. or. April 18, 19S6, at Three Mile Island. Middletown, Pennsylvania.
The purpose of the meeting is to discuss the overall equipment qualification program approaches at the Three Mile Island, Unit No.1 (TMI-1) and Oyster Creek facilities, and, specifically, the recent Performance Appraisal Team unqualified cable finding at TMI-1.
You should be preparec to discuss the following ite.s:
Discuss the r'ethods used t; establish tre r:cster lists for Three Mile Island I and Oyster Cren, list the similarities and dif ferences, Identify from records, to include central and site procurement files, all e
cable types reauiring qualification.
Veri fy and dis:uss wnat methods were used to establish qualifi:& tion (test / analysis).
Discuss what as-built inspe:tions have been performed at TMI-I to verify the sampling process.
Discuss what other connocities or equipment the nonrepresentative sampling techniques were used for in determining the master list.
Discuss the scope of the current inspection and document review performed by your contractor and the results.
If you have any further questions concerning this matter, contact R. Blough (215-337-5051) or J. Durr (215-337-5282).
Your cooperation wf th us in this matter is appreciated.
Sincerely, i
\\f j h. p (! Qr LuN* '
. f., Stewart D. Ebn'e'ter, Director Division of Reactor Safety
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