ML20214K357
| ML20214K357 | |
| Person / Time | |
|---|---|
| Issue date: | 11/14/1986 |
| From: | Cilimberg R, Jocelyn Craig NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| Shared Package | |
| ML20214K229 | List: |
| References | |
| REF-QA-99900005 NUDOCS 8612020275 | |
| Download: ML20214K357 (19) | |
Text
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ORGANIZATION: WESTINGHOUSE ELECTRfC CORPORAT10N NUCLEAR FUEL DIVISION PITTSPURGH, PENNSYLVANIA INSPECTION INSPECTICU REPOPT DATES: 10/06-09/86 ON-SITE P0tmS- 78 NO.- 99900005/86-02 CORRESPONDENCE ADDRESS: Westinghouse Electric Corporation Nuclear Fuel Division ATTN: Dr. Richard Slember General Manager Post Office Box 355 Pittsburgh, Pennsylvania 15230 CRGANIZATIONAL CONTACT: Mr. R. Cost, Manager of Quality Assurance TELEPHONE NUMBER: (4121 374 2359 NUCLEAR INDUSTRY ACTIVITY: Nuclear fuel assembly supplier for Westinghouse (W), -
General Electric, and Combustion Engineering designed reactors.
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(![jy!Q ASSIGNED INSPECTOR: 'Date P/.'j L. Cilimberg, Special Pr ect$' Tnspection
\
Section (SPIS) \
OTHER INSPECTOR (S): C. M. Abbate, SPIS Y.. C. Leu, SPIS
- f. ynr nConsultant f D J. .
' li y s_
APPROVED F,Y- -
Date fahn W. Craig, Chief, SPIS,NVendor Program Branch INSPECTION BASES AND SCOPE:
A. BASES: 10 CFR 50, Appendix B and 10 CFR 21.
B. SCOPE: Review fabrication and testing activities, follow-up on previous inspection findings and fuel problems reported at Vogtle 1, Braidwood 1, and McGuire 1.
PLANT SITE APPLICABILITY:
PWR facilities with fuel supplied by Westinghouse.
8612020275 861134 PDR GA999 EMVWEST 99900005 PDR
ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA INSPECTION REPORT PAGE 2 of 13 NO.: 99900005/86-02 RESULTS:
A. VIOLATIONS:
None.
B. NONCONFORMANCES:
- 1. Contrary to Section 17.1.5 " Instructions, Procedures, and Drawings,"
of the Westinghouse Electric Corporation Water Reactor Divisions Quality Assurance Plan, WCAP 8370/7800, Revision 10A/6A, dated August,1984, and Section 7.1 of Mechanical Operating Procedure (MOP)-730502, Revision 13, dated August 21, 1986, the wash / rinse tank temperatures were observed to be lower than those required by the procedure. (66-02-01)
- 2. Contrary to Section 17.1.5 of WCAP 8370/7800, Revision 10A/6A, dated August,1984 and Section 7.0 of Chemical Operating Procedure (COP)-
814741, Revision 4, dated March 21, 1986, the operator set the revolution counter at 10 instead of 160 as required by the procedure
- for blending a bulk blending container of uranium dioxide. (86-02-02)
- 3. Contrary to Section 17.1.5 of WCAP 8370/7800, Revision 10A/6A, dated August,1984, and Sections 4.2 and 7.1 of COP-814742, Revision 5, l dated August 26, 1986, the sample hood ventilation was not being monitored weekly as required by the procedure. (86-02-03)
C. UNRESOLVED ITEMS:
l None.
D. STATUS OF PREVIOUS INSPECTION FINDINGS:
- 1. ! Closed)Nonconformance(85-01-01)
Centrary to Section 17.1.5, " Instructions, Procedures, and Drawings,"
of WCAP 8370, Revision 10A and WCAP 7800, Revision 6A, dated August, 1984, and Quality control Instruction (QCI) No. 108857, Revision 6, dated October 22, 1984, an autoclave was left uncovered when not in use.
All certified technicians have been reinstructed on procedural requirements for covering autoclaves when not in use. The NRC l
inspectors determined during this inspection that one autoclave was not in use and had been covered in accordance with QCI No. 108857, Revision 6. This item is considered closed.
i f
ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA INSPECTION REPORT PAGE 3 of 13 RESULTS:
N0.: 99900005/86-02
- 2. (Closed) Nonconformance (85-01-02)
Contrary to Section 17.1.5 of WCAP 8370, Revision 10A and WCAP 7800, Revision 6A, and QCI No. 108823, Revision 0, rod pressurization was determined according to 501 R-0618 and not SOI R-0563 as specified by the QCI.
The NPC inspectors determined during this inspection that QCI 108823 was deleted on January 10, 1986. This item is considered. closed.
- 3. (Closed) Nonconformance (85-01-03)
Contrary to Section 17.1.5 of WCAP 8370, Revision 10A and WCAP 7800, Revision 6A, and Product Assurance Procedure (PAP) 2.2.2, Revision 4, dated December 2,1982, management approval sign-off for qualification of a metallurgical laboratory technician was missing from the evaluation sheet.
The qualification record was corrected on November 14, 1985, by the responsible product assurance engineer. The NRC inspectors determined during this inspection that the evaluation sheets for qualification of metallurgical laboratory technicians contain the required management approval signatures. This item is considered closed.
E. INSPECTION FINDINGS AND OTHER COMMENTS:
- 1. Entrance and Exit Meetings Westinghouse management representatives were informed of the scope of the inspection during the entrance meeting. The inspection findings and observations were summarized during 'the exit meeting on October 9, 1986.
- 2. Pellet Fabrication
- a. Transferring Material From Polypaks to a Pulk Container (1) Procedure Review The inspectors reviewed COP-814751, " Transferring Paterial from Polypaks to a Bulk Container," Revision 7, dated March 21, 1986, related to powder transferring from poly-paks into a bulk blend container.
r ORGANIZATION: WEST 1NGPOUSE ELECTRIC CORPORATION NtiCLEAR FUEL DIVISION PITTSBl'RGH, PENNSYLVANI A INSPECTION REPORT PAGE 4 of 13 RESULTS:
N0.: 99900005/86-02 The procedure contains requirements for moisture content, oxygen to uranium ratio limits for powder to be processed, ventilation requirements, and the steps used for the material transfer operation. The procedure was complete and had been properly reviewed and contained the required signature approval.
(2) Observation of Operation The inspectors observed the production of uranium dioxide pcwder for Contract TGAF-01, Blend Number 4099-01. One hundred polypaks of powder were transferred to a bulk container in accordance with Section 7.0 of COP-814751.
Powder moisture content, oxygen to uranium ratio, and ventilation requirements had been determined to be within allowable limits and were signed off, as required, by engineers. The steps of the procedure observed by the inspector were properly followed.
Step 9 of Section 7 of COP-814751 requires two people to verify the visual inspection of a bulk container and sign form CSR-051, " Bulk Blend Status." The NRC inspectors found only one signature on the form and informed the supervisor about the missing signature. The form was properly completed. This observation was discussed during the exit meeting.
- b. Blending Powder (1) Procedure Review The NRC inspectors reviewed COP-814741, " Blending Powder,"
Revision 4, dated March 21, 1986, for bulk blending a container of uranium dioxide. The procedure was found to be technically correct and complete.
(2) Observation of Operations The NRC inspectors observed the blending of uranium dioxide powder for Contract TGAF-01, Blend Number 4098-01. After the bulk container had been positioned in the tumbler blender, the operator set the revolution counter at 10.
This was corrected by the supervisor and the counter was reset at 160 as required by COP-814741.
x
. a ORGANIZATION: WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION-
.PITTSBURGH, PENNSYLVANIA
~
'+ INSPECTION REPORT RESULTS:
~~ PAGE 5 of 13 NO.: 99900005/86-02 s
Nonconformance 86-02-02 was identified in this area.
- c. Quality Control Sampling (1) Procedure Review The inspectors reviewed COP-814742, " Quality Control Sampling," Revision 5, dated August 2,1986. The procedure requires that a Quality Control (QC) inspector designate sample locations, and a health physics technician monitor the sample hood ventilation on a weekly basis. The procedure requires that gloves and face respirators be
' worn while taking samples.
~
(2) Observation of Operations The inspectors observed the sampling of Blend Number 3673-01 for Centract NSLT-0U. The QC engineer designated ten locatiens for sampling at the bottom of the bulk container.
Ten samples were taken from the front to the back, and from the right to the left. Four samples were for chemical analysis, and.six samples for isotopic analysis. The procedure was properly followed during the operations but the NRC inspector determined that the ventilation sample hcod velocity was being monitored monthly intead of the
- weekly frequency required by COP-814742.
Nonconformance 86-02-03 was identified in this area.
- d. Pcwder Re-Milling The inspectors reviewed COP-814746, "Remilling Powder from a Bulk Container," Revision 7, dated March 21, 1986. This is done to control the physical properties of the powder. The
' procedure describes the item, control system (ICS), the safeguards aspect of operations, and thF step-by-step operational instruc-tions for re-milling the powder.
The hRC inspectors observed the re-milling of Blend Number 4099-
~
01 Contract TGAF-UL and the af ter re-nilling of Blend Number 4098-OL for Contract TGAF-01. The steps of the procedures were properly implemented.
ORGANIZATION: WESTlNGHOUSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA INSPECTION REPORT RESULTS:
PAGE 6 of 13 NO.: 99900005/06-02 The NRC inspectors observed that the operator wore a respirator although the procedure does not require one to be worn.
Procedure COP-814746 was revised during the inspection to docu-ment that respirators are being worn by the operators.
No items of nonconformance or unresolved items were identified in this area.
- e. Prepare Bulk Blend for Pelletizing The NRC inspectors reviewed " Prepare Bulk Blend for Pelleting,"
C0P-814748, Revision 7, dated August 24, 1986, and observed blending of Blend Number 5532 for Contract 53E260. The steps of the procedure were properly implemented.
No items of nonconformance or unresolved items were identified in this area,
- f. Press Pellets The NRC inspectors reviewed COP-820201, " Press Pellets,"
Revision 12, dated June 19, 1986, and COP-820202, " Checking Green Pellet Density," Revision 6, dated March 5,1986. The steps of both procedures were being properly implemented while pressing the pellets and checking the pellet density for Contract EAAF-02.
Eo items of nonconformance or unresolved items were identified in this area.
- g. Grinding Diameter Check The NRC inspectors reviewed COP-820a02, " Grinding Diameter Check," Revision 5, dated August 5, 1986, for checking the diameter of pellets af ter grinding. The procedure describes l the test preparation, setup, step-by-step operation and establishes criteria for identifying pellets whose diameters are outside limits.
The steps of the procedure were properly implemented while checking the diameters of pellets for Contract TGAF-01.
I No items of nonconformance or unresolved items were identified in this area.
l I
OPGANIZAT10N: WESTINGHOUSE ELECTRfC CORPORATION Nt! CLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA REPORT IMSPECTION RESULTS: PAGE 7 of 13
.NO.: 99900005/86-02
- 3. Fuel Rod Fabrication The NRC inspectors observed five steps in the fabrication of fuel rods and compared the procedural requirements to the actions being performed by the operators.
The following Mechanical Operating Procedures (M0P) and manufacturing steps were examined: M0P-750603, " Tube Labeling and Tube Weighing Operation Procedure," Revision 14, dated May 8, 1986; M0P-750604,
" Cleaning Fuel Tubes," Revision 6, dated January 18,1986; M0P-750304,
" Fuel Loading of Preplugged Tubes (Bottom Ends) by Vibratory Loader,"
Revision 18, dated June 16, 1986; M0P-750305, " Manual Girth Welding of Fuel Pod Bottom End Plugs," Revision 11, dated February 28, 1986; and M0P-750294, " Manual Pressurization and Seal Welding of Fuel Rods,"
Revision 13, dated March 5, 1986.
Each M0P outlined the purpose, references, terms / definitions, respon-sibilities, regulatory requirements, special precautions, and procedure, which included preparation and operation. The personnel who were observed by the NRC inspectors performing the M0Ps listed above were knowledgeable of the procedures, and followed the steps outlined in the procedures.
An additional area examined in the fuel rod manufacturing process was the equipment calibration and control system regarding ring gages.
The inspector randomly selected ten ring gages located on the shop floor to assure that thev were in the calibration control system and were being calibrated. For the gages selected, the inspector verified that each gage had a record in the tool and gage room and had been properly released to a specific area af ter being calibrated.
No items of nonconformance or unresolved items were identified in this area.
- 4. Fuel Assembly Operations The NRC inspectors observed several steps in the fuel assembly process. The fuel assembly operation begins with the completed fuel rods being loaded into a magazine which hold the rods until they are placed in a fuel assembly skeleton. The procedure is outlined in M0P-730601, " Load Rods Into Magazine," Revision 19, dated August 18, 1986.
ORGANIZAT10N: WESTINGHOUSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION
~
PITTSBURGH, PENNSYLVAMIA REPORT INSPECTION RESULTS: PAGE 8 of 13 NO.: 99900005/86-02 One observation made by the inspector during the review of the activities associated with this procedure involved the traceability of the fuel rods. After the fuel rods were loaded into the magazine, the bar codes used for the traceability of each fuel rod were read into the computer to assure that all the rods in the magazine were in fact OC released rods and the magazine did not contain any defective rods. The inspector observed the operator reading the bar codes into the computer after all but two rows of fuel rods were loaded into the fuel assembly skeleton. Although there is not a procedural requirement which covers when the bar codes are to be read into the computer, there exists the potential to have a defective rod inserted into an assembly before being identified.
After the rods are in the magazine, they are placed in the fuel assem-bly skeleton. The NRC inspectors observed two operators performing this activity as outlined in M0P-730102, " Load Fuel Rods Into Skeleton Assembly - Pull Loaded Assembly," Revision 20, dated August 4,1986.
Af ter a visual inspection of the loaded fuel assembly was performed, the inspector observed MOP-730109, " Fixture Top Nozzle - Pull Loaded Assembly," Revision 28, dated September 9, 1986, being performed by an operator.
The final fuel assembly was inspected utilizing the following QCIs:
OCI 938410, " Fuel Assembly Inspection (Envelope) Using LVOT Probes,"
Revision 24, dated June 16,1986; QCI 938420, " Fuel Assembiy Inspection (Tilt and Length)," Revision 40 , dated June 23, 1986; QCI 938a35, " Fuel Assembly Inspection Channel Spacing," Revision 35, dated July 7, 1986; and OCI 938440, " Fuel Assembly T/N Weld and S-Pole Location Inspection," Revision 14, dated June 23, 1986.
The NRC inspectors observed that the CCIs listed above were performed by personnel as required, and no items of nonconformance were identified in this area.
During the observation of the fu~el assembly final cleaning process, the NRC inspectors noted that a fuel assembly was in Tank 2 and that the temperatures of the wash / rinse tanks were as follows: Tank 1 -
142 F, Tank 2 - 162 F, Tank 3 - 122*F. Section 17.1 of M0P-730502,
" Fuel Assembly Cleaning - General," Revision 13, dated August 21, 1986, requires that the wash / rinse tank operating temperatures be as follows in preparation for cleaning fuel assemblies: Tank 1 - 145 F to 175 F. Tank 2 - 165 F to 180 F, Tank 3 - 145 F to 195 F. The NRC inspectors were informed by the shop floor supervisor that maintenance I
i
ORGANIZATION: WESTlNGH0VSE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA INSPECTION REPORT PAGE 9 of 13 RESULTS:
N0.: 99900005/86-02 work had been performed on the tanks earlier in the day and the tanks were not yet at operating temperatures. However, an assembly was being cleaned in Tank 2. A deviation notice was written for the three fuel assemblies which were cleaned after the last temperature reading was taken which required that the three assemblies be recleaned. The NRC inspectors determined that these three assemblies were cleaned again with the wash / rinse tanks at the proper temperatures.
Nonconformance 86-02-01 was identified in this area.
Two quality packages were also reviewed. The packages were for completed fuel assemblies, 5A01 and 5A02, in the GAAF01 contract for the Vogtle Nuclear Power Plant. The quality packages contained the Quality Release, which certifies that the assembly was fabricated properly, the Folder Acceptance Index, QC Fonn 253, Revision 17, and the Fuel Assembly Routing Sheets. Each routing sheet covers a specific part of the manufacturing process and lists the sequence of steps, description, operation number, revision being worked, the ope"ator's initials and the bill of materials. The two packages reviewed contained the required information and no items of nonconformance were identified.
- 5. Fuel Skeleton Assembly The NRC inspectors observed some of the steps in the fabrication and inspection of the fuel skeleton assembly and determined that work observed was being performed in accordance with M0P-731101, " Assemble Skeleton," Revision 23, dated September 9,1985. Skeleton components such as thimble tubes, grids, shoulder screws, plates, and nozzles were checked against routing sheets to ensure that the serial and part t
numbers matched the identification specified for each fuel assembly l' for a specific contract number. Thimble tubes and shoulder screws were loaded in a grid in accordance with M0P-731214 " Mechanical Assembly," Revision 8, dated August 13, 1986. The thimble tubes were crimped inside the grid sleeves in accordance with M0P-731214. The torque on the shoulder screws was verified in accordance with QCI j
936110, " Thimble Tube Probe," Revision 40, dated August 11, 1986. The inside diameter of the thimble tubes were examined for cracks with a boroscope in accordance with QCI 936101, "Expar.sion Joint Quality,"
Revision 33, dated August 4, 1986.
No items of nonconformance were identified in this area.
l
[
ORGANf2ATION: WESTfNGHOUSE ELECTPIC CORPORAT10F NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA I
INSPECTION REPORT RESULTS:
PAGE 10 of 13 NO.: 99900005/86-02
- 6. Nondestructive Testina (NDT)
The NRC inspectors reviewed Westinghouse procedures for ultrasonic testing (UT), radiographic testing (RT), helium leak testing (LT),
gamma scan and the NDT certificatiot, program for the NDT of fuel rods.
The procedures were technically correct and complete. The procedures had also been properly reviewed and contained the required signature approval. The NRC inspectors observed operators performing NOT utilizing these procedures. Observations of the NDT testing and review of the NDT certification program are itemized below:
- a. A technician performed circumferential and axial ultrasonic scanning of zircaloy fuel rods in accordance with QCI 920103,
" Ultrasonic Testing of Fuel Rod Welds," Revision 10, dated October 6, 1986.
The technique used was in accordance with the written procedure and the required documentation was properly completed.
Additionally, the control of the chuck pressure used to hold the rods during UT was reviewed to assure no indentation of the rods occurred after release from the jaws. The procedure listed a maximum pressure to be applied and this requirement was properly implemented.
- b. A technician was observed performing radiographic inspections as described in QCI 920102, " Girth and Seal Weld X-Ray, Seifert X-Ray," Revision 34, dated September 29, 1986. The steps of the procedure were properly followed and the results were documented.
- c. A technician was observed reviewing radiographs and processing i
film in accordance with OCI 928105, " Densitometer Operation,"
Revision 12, dated October 8, 1984, QCI 928106, "X-Ray Film l
Processing (Automatic)," Revision 6, dated February 17, 1986 and QCI 920101, " Weld Radiographic Inspection-Film Reading,"
l Revision 64, dated October 6, 1986. All steps of these procedures were properly followed and the results were documented.
ORGANIZATION: WESTINGHOUSE ELECTRIC COPPORATf0N NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA REPORT INSPECTION RESULTS: PAGE 11 of 13 N0.: 99900005/P6-02 Additionully, three completed radiographs were reviewed by the NPC inspector to assure that proper disposition and documentation was achieved. In these instances, the proper disposition and documentation was in accordance with the applicable procedure.
- d. A technician was observed calibrating and operating the helium leak tester to confirm the integrity of the assembled rods. The procedures used during these operations are QCI 928021, " Helium Leak Test (Equipment Operation)," Revision 12, dated November 25, 1985 and OCI 922101, " Helium Leak Test (Inspection Requirements),"
Revision 36B, dated March 31, 1986. The steps in these proce-dures were properly followed and the results were documented.
- e. The NRC inspector observed gamma scanning. The results of this test provide data on enrichment, gaps in the fuel stack, spring insertion and length of fuel in the rods. Observation of scanning verified that the steps of OCI 923103, " Gamma Scan,"
Revision 32A, dated August 22, 1986 were properly followed and the results were documented.
- f. Training and Qualification of Nondestructive Test Personnel The training and oualification records of four nondestructive test personnel were reviewed to assure compliance with the Quality Control Training Panual, Revision 2, dated October 11, 1983, the Quality Control Manual dated July 14, 1986, and OCI 000134, " Nondestructive Testing Certification Program,"
Pevision 5, dated March 17, 1986. Documentation describing examinations and reccrd of training was complete.
During the review of the actual testing for radiographic film interpretation, it was observed that questions recuiring true or false responses were written in such a manner that either the true or false response would be correct. This was deter-l mined by reviewing actual tests and confirming that both the true and false response were considered correct. This obser-l vation was discussed during the exit meeting on October 9, 1986.
No items of nonconformance were identified in this area.
ORGANIZAT10h: WESTINGHOUSE ELECTRfC CORPORATTON NUCLEAR FUEL DIVISION PITTSBURGH, PENNSYLVANIA INSPECTION REPORT RESULTS:
PAGE 12 of 13 N0.: 99900005/86-02
- 7. Fuel Incidents at Reactor Sites The NRC inspectors reviewed selected information concerning fuel incidents which have occurred at reactor sites which may have been caused by steps in the manufacturing process. Information was obtained during a meeting with site personnel which included a conference call to Westinghouse (W) design personnel at Monroeville, Pennsylvania. The results of this review are as follows:
- a. Incorrect Burnable Poison Orientation at Braidwood 1 Burnable poison (BP) assembly C5aF arrived at the Braidwood site with the BP rods oriented 90 degrees from the correct position in the BP bundle. W's analysis concluded that the BP rods had been incorrectly orTented because the thimble plugs had been attached in the wrong holes in the holddown assembly. Procedure MOP-732220, " Assemble B/P-Source Assembly," Revision 15, dated March 18, 1986, was revised after the Braidwood incident to require that thimble plugs be matched with the specified traceability document to prevent a recurrence of this problem.
- b. Incorrect BP Orientation at Vogtle 1 Two BP assemblies arrived at the Vogtle site with the BP rods oriented in locations which did not meet the design requirements for the Georgia Power order. W's analysis concluded that BP rod location symbol was drawn for core component type M10BP on W -
Drawing Number 1848E27, "A.W. Vogtle 1 Core Loading Plan Cycle 1," Revision 2, dated April 29, 1986. The two BP assemblies were manufactured according to this incorrect symbol.
The symbol was drawn by a W engineer. W has instituted a requirement for an indepen3ent check of all core loading plans by an engineer who did not draw the location symbols on the plan being checked. This independent check was initiated by W to minimize the possibility for a recurrence of this problem.
- c. Dents in Fuel Rods at Vogtle 1 Fuel rods arrived at the Vogtle 1 site which exhibited dents on the outside surface of the cladding. W determined that the dents were caused by the chuck on the ultrasonic testing (UT) machine.
The most severe dents exhibited a maximum depth of 0.0007 inches based on metallographic examination of the two most severely dented fuel rods. The allowable W dimensional tolerance on
ORGAN 12ATION: WEST 1NGP0USE ELECTRIC CORPORATION NUCLEAR FUEL DIVISION
- PITTSBURGH, PENNSYLVANIA INSPECTION REPORT PAGE 13 of 13 RESULTS:
NO.: 99900005/86-02 surface defects such as dents is 0.001 inches in depth. The dented fuel rods were accepted on a deviation notice -
disposition request (DNDR) because the dents were less than the allowable 0.001 inches in depth. Dents have been eliminated in subsequent fuel rods by reducing the chuck pressure on the UT machine. This was reviewed as discussed in Section 6(a) above.
- d. Bowed Fuel Assemblies at Vootle 1 Fuel assemblies arrived at the Vogtle I site which did not meet the envelope dimensional requirements for bow. W reworked the assemblies to remove the bow, but the bow returned immediately after rework. Transfer waiver requests (TVR) have been issued by W to accept bowing on fuel assemblies for all contracts until drawings can be changed per engineering change notices (ECN).
- e. Loose Fuel Pellets in McGuire Unit 1 On June 27, 1986, ten pellets were recovered from McGuire Unit 1.
The top six inches of fuel rod number 16 in fuel assembly D-03 was missing and fuel rod number 15 was deflected two inches from vertical at the top. W suspects that the cause is associated with faulty fuel handlTng and/or baffle jetting. W concludes that these incidents were not caused by fuel fabrication.
F. PERSONS CONTACTED:
C. Alstadt J. Hall G. Sinkler
- J. Hart N. Spears J. Barker *N. Storrs J. Bond B. Hartnett
- J. Higginbotham C. Taylor L. Burton T. Riley
- J. Hubich
- J. Bush T. Ryans D. Campbell *P. Kays
- E. Keelen B. Schumpert
- H. Corey K. Singleton
- R. Cost *C. LaBruyere
- E. Loch E. Sparrow F. Culus N. Stevenson T. DeCristofard H. Menke
- J. Donovan C. Mitchell R. Talbert
- S. Patrick B. Weaver G. Duke c
l A. Engel R. Perkins C. English *R. Pollard
- W. Goodwin E. Quarterman
- B. Green-Field F. Shaffer j T. Silvey E. Griffin
- attended exit meeting
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