IR 05000320/1976006
| ML19207B175 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/02/1976 |
| From: | Finkel A, Heishman R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19207B171 | List: |
| References | |
| 50-320-76-06, 50-320-76-6, NUDOCS 7908230494 | |
| Download: ML19207B175 (18) | |
Text
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~ - O p1g~ 7, - f f J J 8"J _ /" ' - REGIO:1 I .o Jt -- ) [ 50-320/76-06 50-320 IE Inspection Report u..o : Docket io: s , h Metropolitan Edison-Company CPPR-66 L, cense No: ,; Licensce: . . ~~ Priority: .e Reading, Pennsylvania 19603 A (p Category: tE Q Safeguards --
- "E Middletown, Pennsylvania. (TMI-2)
Loca tio n: .
- PWR 959 MWe ( Ta & W) Type of Licensee: Routine, Announced Type o:m Inspec t io n.
. . . May 10-13, 1976 Dates or Inspection:
Dates cf Previous Inspec tion:
_ / , Reperting Inspector: ,QAfM d [, M d .2' 75 Li Narrow, Reactor Inspector / DATE I [ ~2 / '
. . Acconpanying inspectors: _,, A.
Finkel/ Reactor Inspector DATE f %4#~ 4/2J76
' G.
Walton, Reactor Inspector DATE-a w -:q . [1* i DATE % 'j Other Accompanying Personnel: NONE
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SUMMARY OF FINDINGS Enforce =ent Action . ' Items of Noncomoliance Infraction s Contrary to 10 CFR 50, Appendix B, Criterion XII, crimping tools in use for terminating safety-related cable and wire had not been controlled and calibrated as required by the specifications.
(Details, Paragraph 2) i Licensee Action on Previously Identified Enforcement Items Material certifications for welding material and structural bolts for the core flood tank support structure have been provided by the vendor, reviewed by QA and incorporated into the data package.
(Details, Para-graph 3.b) Desien Chances
' None.
Unusual Occurrences
- ! None.
i Other Sienificant Findings A.
Current Findings 1.
The following ite=s are unresolved: ~ a.
Review of 3&W Field Construction Procedures (FCP's) show , j that procedures applicable to the work have been replaced t by later revisions and are not available nor referenced in the docu=entation. package.
(Details, Paragraph 4) ,,. - , b.
The requirements for separation or installation of barriers - between redundant electrical channels or between safety- - _ related and non-safety-related channels in certain panels - - e . e-o e e* L - - l.
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This item has been identified by the licensee et. Deviation Report
(DR) 0586.
(Details, Paragraph 5) 2.
The following ite=s are considered to be acceptable: , a.
Velding 'in progress on safety-related piping.
(Details, Paragraph 6) s.
b.
Documentation of welding on reactor coolant pressure boundary (RCPB) and other safety-related piping.
(Details, Paragraph 7) c.
Receiving and installation inspection documentation for core flood tank B supports.
(Details, Paragraph-10) d.
QC procedures for instru=entation.
(Details, Para'- graph 8)
l e.
Installation of electrical equipment and cable termina-I tions.
(Details, Paragraph 9) I l B.
Previously Reported Unresolved Ite=s , - The following items have been resolved: 1.
The requiremerts of the FSAR Technical Specifications and ASME Section XI have been included in the pre-service inspec- , tion program.
(Details, Paragraph 11) '
2.
Procedure ECP 3-2 has been revised to include requirements , for temperature conditioning of electrical cables-(Details, Paragraph 12) , f 3.
Docu=entation for structural steel has been provided and j identified with respect to purchase orders and specifications.
(Details, Paragraph 3.a)
j 4.
Visual examination of the reactor ir_ernals has verified that the two missing shims had not oeen left in the internals.
, (Details, Paragraph 13) - , i ! . c,i,d.o fs a J A. o ) i i .i' i
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Nonconfor=ance t.0 cleanliness requirements of the reactor internals which had been reported by the licensee has been ,j corrected by re-cleaning of the equipment and area and installation of protective coverings.
(Details, Paragraph 14) 6.
The void in the wall of the fuel handling building at west ' transfer tube has been filled by grouting.
(Details, Para-graph 15) s C.
Deviations None.
Exit Interview j An exit interview was held at the site on May 13, 1976.
Persons Fresent . General Public Utilities Service Corporation W. T. Gunn, Proj ect Site Manager R. F. Fenti, QA Auditor S. Levin, Project Engineer P. A. Levine, QA Auditor M. A. Nelson, Technical Engineer M. J. Stromberg, Sr. Site Auditor J. E. Wright, Site QA Manager United Engineers and Constructors G. T. Cavis, Project Superintendent J. Carrabba, Assistant Superintendent ! S. B. Dutta, Assistant Piping Engineer D. C. Lambert, Field Supervisor QC , ! R. W. Liscom, QC Electrical Engineer C. W. Hunter, Electrical Supervisor i.
E. L. Sondahl, Instrunent Supervisor I Burns & Roe W. P. Dornsife, Proj ect Engineer . Babcock and Wilcox
R. J. Kunr, QC Supervisor
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The items discussed are su==arized.below.
In each case, the licensee acknowledged the infor=ation.
A.
Scope of Inspection The inspector stated that the inspection was conducted to review ' the status of outstanding items and the QC program for safety-re-lated piping, electrical and structural work.
s B.
Items of Noncompliance i The inspector discussed the use of uncalibrated crimping tools for termination of safety-related cable and wire and stated that this is considered to be in noncompliance wit'.i 10 CFR 50, Appendix B, Criterion XII.
(Details, Paragraph 2) C.
Unresolved Items , The inspector discussed the items listed under part A.1 of Current , Findings of the Su==ary of Findings and stated that these icens are unresolved.
(Details, Paragraphs 4 and 5) D.
Accentable Items , The inspector identified the items listed under part A.2 of Current Findings of the Su ary of Findings and stated that these itecs had been ins ected with no discrepancies identified.
(De tails, Paragraphs 6, 7, 8, 9 and 10) E.
Previousiv Reported Items The inspector discussed the ite=s listed under Previously Identi-fled Enforcement Ite=s and Unresolved Items of the Su=-.ary of Findings and stated that these items are resolved.
(Details,
Paragraphs 3, 11, 12, 13, 14 and 15) ,
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-< _ . . _ - - . . ' ... ! I DETAILS 1.
Persons Contacted General Public Utilities Service Corporation .' R. F. Fenti, QA Auditor W. T. Gunn, Project Site Manager R. W. Heward, Project Manager S. Levin, Project Engineer P. A. Levine, QA Auditor M. J. Stromberg, Senior Site Auditor R. J. Toole, Test Superintendent J. E. Wright, Site QA Manager United Engineers and Constructors ' S. Abbott, Welding Superintendent J. Carrabba, Assistant Superintendent, QC-Construction R. Dourte, Assistant QA Supervisor J. Godleski, QA Ergineer B. Herchelroth, QC El-ctrical j C. W Hunter, Electrical Supervisor j D. Lambert, QC Supervisor R. W. Liscom, QC Engineer, Electrical . l A. Morris, Piping Supervisor E. Somdahl, Instrument Supervisor J. Tyndall, Welding Supervisor Babcock and Wilcox R. Kun, QC Supervisor 2.
Control of Crimoing Tools During a previous inspection (Inspection Report No. 50-320/75-14) ' lack of a procedure for control and periodic calibration of i crimping tools had been identified as an unresolved item.
The
tools at that time were not in use on safety-related cable or
wire.
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( ( ' . . . t-6- ._ The inspector deter =ined that cri= ping of safety-related cable , and wire had been performed using uncalibrated tools since February, 1976.
Circuits which had been terminated usit4 these tools include: Nuclear Service Cooling pu=p discharge valve power cables, river water pump motor power and control cables and viral power supply control cabinet viring.
At a meeting with the licensee's representatives, the inspector was informed: a.
ECP 3-2 had been revised (Revision 14) in March,1976, to require that cri= ping tools be calibrated at two conth intervals.
The inspector confirmed this revision but ob-served that detailed calibration procedures were not avail-able.
b.
Hand tools had been provided with serial numbers and we're issued by badge nu=ber of the employee for control and to enable recall of tools for calibration purposes.
c.
Calibration of tools was in progress.
A total of 77 tools - had been issued.
Of these, 37 had been calibrated.
None of the tools calibrated to date had been found to be out of tolerance.
d.
Instructions had been issued to the field that cri= ping of safety-related cable and wire was to be perfor=ed using calibrated tools only.
Cri= ping of wire sizes for which . calibrated tools were not available was to be discontinued.
The use of uncalibrated crimping tools on safety-related cable and wire ter=inations and their release for such work without establishment of measures for their control, calibration and , adjustment is contrary to the requirecents of 3&R Specification No. 2555-70; Paragraph 3.1.1.2.c (Table 1 and 2) of Section 16A and Paragraph 3.1.2 of Section 16D.
This is considered to be in noncompliance with 10 CFR 50, Appendix B, Criterion XII, which . states: " Measures shall be established to assure that tools, gages, instrutents, d measuring and testing devices used in activities r affecting quality are properly controlled, calibrated, and adjusted at specified periods to caintain accuracy within necessary limits.
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Vendor Documentation During examination of vendor documentation for the core flood tank supports (Inspection Report No. 50-320/76-01) the inspector had identified: (1) Lack of material certifications for welding =aterials and structural bolts as a nonco=pliance, and; (2) Failure to clearly identify the applicable specification for each release for procure =ent of =iscellaneous structural steel as an unresolved item.
The licensee had obtained the missing =aterial certifications.
In addition, vendor documentation for miscellaneous structural steel purchased under PO No. 9459.02-18-1 as well as five additional purchase orders for miscellaneous structural steel had been reviewed to determine that docu=entation was co=plete and that the caterial had been purchased to the proper specification.
I The inspector examined the report of the documentation review and j audited documentation as shown below for the P.O.'s 9459.02-18-1
and 9459.02-18-12.
.* i - a.
Vendor documentation for P.O.
18-1 This order had been filled under a large a=ount of separate " Releases," 64 of which had been identified as providing safety-related material.
The inspector examined docu=entation for Releases Nos.
2, 4, 54, 59, 64, 72 and 129 for structural - shapes, plates and anchor bolts and observed that Certificates ' of Compliance or Mill Test Reports were included in the docu=en-tation packages and conformed to the specification requirements i for the caterials.
i b.
Vendor documentation for P.O.
18-12 - Structural supports for the core flood tanks had been furnished under this purchase order and in acco* dance with the vendors drawings L 73-23 El sheets 5 and 6.
The inspector examined these drawings and Mill Test Reports for the heats identified i on these drawings as well as Certificates of Co=pliance for structural bolts.
Anchor bolts for these supports had been
supplied under P.O. 18-1.
These items are resolved.
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Field Installation Records The inspector reviewed records of field installation of piping - performed by Babcock and Wilcox Company (B&W) consisting of Field Construction Procedures (FCPs) showing work sequences perfor=ed and where applicable the detailed procedure for perfor=ance of the sequence.
The inspector noted that in many cases the detailed procedure had been replaced by a later revision and the procedure used was not referenced and was not available in the documentation package.
For example; the radiographic procedure 9T-RT-203/c-6 in a docu=entation package is dated September 30, 1975.
The work sequence for radiography in the FCP which referenced procedure 9T- > RT-203/c-6 was signed off as completed on October 22, 1974.
The documentation package does not identify the revision of this pro-cedure which was applicable at the time the work was performed nor is that procedure included in the documentation package.
The inspector reviewed FCP's Nos. 7, 8, 9 and 10 and noted that in each case some of the procedures included in,the documentation package were dated af ter the work was shown to have been performed.
This condition was identified for weld instruction and NDE proce-dures.
The licensee's representative stated that it was their policy to destroy outdated revisions to procedures when new revi-sions were issued.
. The inspector stated that a complete review of the documentation could not be performed without identification of the applicable procedure revision as of the date of performance of the work and without provision of a copy of that revision in the documentation package.
The inspector was informed by the licensee's representative that j copies of revised procedures would be furnished to the site by
B&W and would be retained as part of the documentation package so i as to be available for review.
This item is unresolved pending review of the FCPs and applicable procedures by the NRC inspector.
i 5.
Wire Seoaration A review of the licensee audit report by the inspector indicated that a problem exists in maintaining a mini =um separation of 6" between safety-related wiring and non-safety-related wiring.
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This situation exists in the following ite=s: DC Panels DCA 1A, 2A; DCC 1A, 2A; DCW lA, 2A; DC switchgear 1-IDC, 2-IDC; panel 19; control console 6B, E; 480V unit sub. 2-31E, 2-41E; 4 KV switch-gear 2-3E, 2-4E and 480 V MCC's 2-11EA and 2-21EA.
Reference deviation report 0586 dated April 27, 1976.
This item is unresolved pending review by the NRC inspector of action taken to resolve this problem.
6.
Welding of Safety-Related Piping The inspector observed work in progress on welding of safety-related piping as shown below.
a.
Decay Heat - Weld No. 2-DH-50W This is a 3-inch schedule 40 line; the caterial is A376,- type 304.
Welding was approxi=ately 75: complete.
Weld ' procedures no. 20 and no. 8 were followed using 3/32-inch diameter type 308L filler cetal.
A visual inspection of the wald root had been =ade.
The weld angle and appearance of the weld were observed.
The welder identification (2S) and weld identification (2-DH-50W) were established by permanent ! carkings adjacent to the weld.
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b.
Make-Up and Purification - Weld No. 2-MU-56W , This is a 2 1/2 inch schedule 160 line; the material is ! A376, type 304.
Fit-up of the joint was complete with an ' EB weld ring installed in preparation for welding.
The EB ring is type ER 308L.
. The inspector observed the weld identification, joint align-l ment and QC personnel perfor=ing a visual inspection for co=pliance with applicable standards.
c.
Chemical Addition - Weld No. 4A-1 This is a 1/2 inch schedule 160 line; material is A182, Type 304.
Welding was completed and QC inspection had been performed.
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1j-10-The inspector observed.the surface finish of the weld to determine its acceptability for nondestructive ex mination.
The finish was considered to be suitable for visual and PT examination.
The welder identification (22L) and weld identification (4A-1) were af fixed adjacent to the veld by I per=anent markings.
l No discrepancies were identified during observation of this ,' l work.
7.
Field Installation Records a.
Reactor Coolant Pressure Boundarv Piping The inspector reviewed selected field installation records for conformance to the requirements of USAS B31.7 as shown below: } (1) Heat traat=ent at4 accumulated post weld heat treatment times.
(2) Procedure qualification for velds at te=perature ranges of 1050*F to 1250*F.
(3) Nondestructive exaninations including magnetic particle , examination and radiographic examinations af ter final post veld heat treat =ent.
(4) Weld identificaticu traceability.
. b.
The field installation records selected for review included: ' . I l (1) FCP #7 Asse=bly A24-2 (Welds WS-6-4 and WJ-6-3) Ie j (2) FCP #8 Assembly B67-1 (Welds WJ-5-1 and WJ-2-1) t (3) FCP #9 Asse=bly A57-1 (Welds WJ-5-2 and WJ-2-2) J ' (4) FCP #10 Asse=bly A57-2 (Welds WJ-5-4 and WJ-2-2) Except as noted 1.n paragraph 4 above, no discrepancies were identified.
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Other Safety-Related Piping The inspector reviewed field installation records of the following velds for conformance to the require =ents of USAS B31.1 and USAS B31.7.
Weld 2 MU-56W; Make-up and Purification System - Weld 4 A-1; Chemical Addition System Weld 2 DH-50W; Decay Heat System Records reviewed included: Welding Procedures No. 20 and No. 8 Welder Qualifications for welders identified by Nos. 29-A, 22-L and 2-S.
Process control for sequence of fabrication operations.
. Weld filler material issue cards.
No discrepancies were identified.
8.
QC Procedures - Instrumentation The inspector audited UE6C procedures as listed below for handling, storage, installation inspection and testing of instrucentatica cable, terminations, componente and systems.
a.
Electrical Construction Procedure (ECP) ECP-3-2, Revision 14, dated December 1, 1975 for Receiving, Storing, Handling and Installing Wire anc Cable.
This procedure defines the QC requirements for inspection and record keeping during receipt, on-site storage, identification, and docu=entation of quali-fication tests.
This procedure also establishes the require-nents for cable and wire handling and installation; inspection of conduit and cable trays; cable identification, color coding, separation and redundancy; and wire-way loading.
b.
Mechanical Construction Procedure (MCP) MCP-14-2, Revision 7, dated March 9, 1976 for Installation of Instruments.
This procedure defines the requirements for receiving, storage, handling, protection and installation of instruments.
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Electrical Construction. Procedure (ECP) ECP-10-2 for receiving, storing, handling and installing instrument control centers, j cabinets, consoles and instruments racks.
This procedure defines the requirements for the items listed in the pre-ceeding sentence.
, No discrepancies were identified.
. 9.
Installation of Electrical Ecuiement and Cable Ter=f nations The inspector audited installation of the ite=s listed below: a.
DC Power System (Red) , The battery system in the red battery roum EE-H-2-1; rectifier EE-J-2-1A; switchgear with 250 VDC bus and associated breaker EE-H-2-IDC; load center panel EE-H-DCC-1A; and a vital' power supply EE-G-2-lV and associated cable and wire installation.
Installation of these items had been co=pleted prior to the ) inspection.
Their installed condition was examined by the inspector and found to comply to the require =ents of Procedures ECP-3-2, QC-2-2; ECP-5-2 and IMI TP-250/2.
The inspector audited the QA/QC turnover data package for the DC power system described above.
The turnover data package consisted of QC final acceptance sheets, QC punch list, QC final acceptance inspection check list, piping exception list i and turnover agreecent for phase 1 testing.
b.
Electric Motors and Eleccric Valve Operation The inspector audited the installation of motors for the river i water 4160V pumps, cotor operated valves and associated power { and control cables.
Table I indicates the cotors and circuits
which were audited.
i f 4160 Motors Power Cables Control Cable NR-P-1A HJ-7P 3c/110 EJ-8 NR-P-lC HK-19P 3/10 HK-20 MV-P-1A HG-45P Valve Operators
NR-V-2A SE 12 SE 13 N/A NR-V-2B SG 19 SE 20 N/A , NR-V-2C SF 13 SF 14 N/A NR-V-2D SF 21 SF 22 N/A '($2.1.C7
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Other Electrical Equipment and Components . The inspector audited the installation and data package of the following items: Containment ventilation fan motors, (Red) 125 volt DC/120 volt AC instrumene^. tion and control power system, a vital instrument AC power panel, and a 250 volt DC bus and associated breakers.
The table below lists the circuits and equipment which were audited.
Item Designation (1) Containment Ventilation fan motors Motors 100 hp.
(2) (Red) 125 VDC/120 VAC Instrumentation and Motors llA thru s control power system.
. E of Panel 2-IV.
(3) (Red) Vital instrument AC panel Circ.2L1 of Panel 2-IV ~ . (4) (Red) 250 Volt DC Bus and Breaker 2-3V.
- ~ ~ ~ > The inspector examined installation records and procedures, receiving reports and test data.
. ' d.
Electrical Power and Control Cables The inspector audited the following safety-related cables, terminations and associated hardware for the electrical circuit.
shown below.
The inspector verified the circuits installed against the pulling reports and termination reports.
The installation, color coding, tray loading and termination were in accordance with the requirements of UESC ECP-3-2 Revision 14.
, Circuit Fulling Report # Termination Reoort # t HJ-7P 12,115 DR 0539 12,962 ECM 3416 i HJ-8C 11,747 14,090 l HK-19P 11,734 12,964 ECM 3416
HK-20C 13,835 14,067
SE-12P 11,720 11,785 SE-13C 11,742 13-993 SE-19P 12,390 13,950 SE-20C 12,441 13,988 SF-13P 11,721 11,786 SF-14C 12,431 13,991 SF-21P 11,723 11,787 SF-22C 12,436 13,990
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' V ( . . - -14-I The QC turnover data packages confir=ed confor=ance to the specification requirements except for the use of uncalibrated crimping tools and the unresolved item concerning wire separa-j tion identified above.
(Paragraphs 2 and 5)
Except as noted above no discrepancies were identified.
10.
Site Installaticn Records - Core Flood Tank Supports , The inspector examined the documentation listed below for receiving and installation inspe tion of supports for core flood tank B.
a.
Receiving inspection report dated August 16, 1973 with material released by Release Tag No. 920-2.
b.
Receiving report for base plates dated February 21, 1974 and material released by Release Tag No. 112-2.
c.
B&W FCP No. 16 for erection of Tank B.
Sequence No. 070, " Verification that grout (under base plate) has reached design strength" had not been completed and was not signed off by QC.
i j d.
Report of Nonconfor=ity No. 123 identifying lack of full penetration veld.
Disposition of this nonconformity was l established as a requirement to recove the weld and reweld.
The reweld was completed on February 13, 1976 and was re-ported on inspection Report No. 32819.
e.
B&W Inspection Reports:
[ (1) No.
4584 - Dimensional check of centerlines and elevations.
(2) No. 32697 - Visual inspection and " Turn of Nut" method for tightening bolts.
- (3) No. 32819 - Visual inspection of welds for disposition of UE&C DR 0550 - clears Report of Noncon-formity No. 123.
No discrepancies were identified.
11.
Pre-Operational Inspection Lack of a formal pre-operational base-line examination program , had been identified as an unresolved item.
(Inspection Report ' 50-320/75-10) " 3%.1.C3 <' s m =n+wmgg-urm- -5{s % -5.~~.QYk$ddiQWS+0&cy&:m&mna~.w-w&y..v,cw:Q-{$=T&:.p?.5
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O O . . . -15- , i The preoperational inspection program was examined by the inspec-tor and was found to conform to the requirements of the Technical Specifications and of ASME Section Il.
' . This item is resolved.___ _. _ _ j , 12.
Tecoerature Conditioning of Electrical Cable ' . Failure to include provisions for te=perature conditioning of cable prior to cable pulling in procedures had been identified as an unresolved item.
(Inspection Report 50-320/75-14) The inspector examined Electrical Construction Irocedure (ECP) 3-2, Revision 12 dated February 23, 1976.
Paragraph 4.2 of this procedure states, in part, " Cable / wire shall not be removed from reels if it has been exposed to te=peratures below 0*F., within the twenty-four hour period ic=ediately preceding the planned pull.... Reels shall be moved, avoiding i= pact, to a war = area (at N 70*F for twenty-four hours) to condition cable."
. This 1 tem is resolved.
13.
Inventory Discrepancy - Reactor Internals Shi=s A discrepancy between the inventory list supplied with the reactor internals and a count of the shims supplied had been identified as an unresolved item.
(Inspection Report 50-320/76-02) ~ The inspector examined the documentation listed below which iden- , i tifies the problem, describes the ef forts to locate the missing shi=s and the conclusion reached.
a.
Deviation Report (DR) No. 0555 which describes the problee and dispositions it by requiring a joint inspection of the reactor internals and reactor vessel by B&W and UE&C.
b.
Letter dated February 10, 1976 to UE&C and 36W from GPU requesting the inspection noted above.
c.
UE&C Inspection Report Nos. M-7080 and M-7081 reporting visual inspection of plenum, lower internals and support shield using
. flashlights and mirrors.
I
. WZ110 _ a y g g % ' % e w ~6+s.; rich = EME+m=?? & % iisicy@ m;&.M dB $, @ K Q [f=& %
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B&W Inspection Report Nos. 32730 and 32821 reporting visual inspection of upper plenum and core support asse=bly without finding the two missing shims.
, B&W site problem report no. 61 describing the problem, e.
stating that site QC verifies that all shims received are - accounted for and recommending acceptance "as is."
. f.
Letter dated March 22, 1976 from B&W to GPU referencing inspections and concluding that the two missing shims are not in the core barrel or plenum assembly.
On the basis of the above DR No. 0555 was closed with no further action necessary, i This item is resolved.
14.
Cleanliness Reauirements ' On February 18, 1976 the licensee telephoned Region I to report that during installation of the reactor internals vent valves the class "B" cleanliness requirements of the reactor vessel internals and vent valve had been violated.
DR No. 0561 had been written requiring re= oval and reclezning of the vent valves and recleaning , . of the exposed portion of the internals.
The inspector examined: a.
B&W Report of Nonconformity No. 125 reporting that the reactor internals had been downgraded for Class "B" to Class "C" cleanliness during installation of vent valves.
This report showed the disposition completed on February 26, 1976 and referenced B&W Inspection Report No. 32965.
b.
UESC Level 2 Surveillance Report dated February 16, 1976 which reported that DR No. 0561 was issued for violation of class "B" cleanliness; work was stopped and.the reactor vessel covered.
c.
UESC Level 2 Inspection Report dated February 16, 1976 reporting that the vent valves had been installed and cleanliness re-quirements violated.
! YN.1.k E 4 M @ $a;fF$f @ m b % s s ytrt= w m e e r w a y$455 $3f4 $m@ $ $e VM %%R Qis$%NW55F5ALj p m cmww m.-
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UE&C Inspection Report M-7065 witnessed removal, washing and replacing of vent valves.
Two vent valves could not be re-moved.
(This item was reported separately by the licensee en February 20, 1976.)
i I B&W Deviation No. 1 to FCP86 for upgrading cleanlinese conditiou e.
j of vent valves and exposed portion of internals to class "B".
. ' f.
B&W Inspection Report 32965 clearing Report of Nonconformity No. 125.
g.
DR No. 0561 which describes and disposition this deviation; verifies the disposition end closes out the deviation.
This item is resolved.
15.
Vofd in South Wall of Fuel Transfer Building On March 19, 1976 the licensee reported, as a significant defi-ciency in accordance with 10 CFR 50.55(e), that a void had been identified in the south wall of the fuel transfer building around the west fuel transfer tubes.
This area had been blocked out during construction of the wall and the block out filled with concrete after installation of the fuel transfer tube.
The void was the result of inco=plete filling of the blockout.
( The inspector examined the following documents: , a.
DR No. 0563 which described the problem.
Disposition re-quired drilling holes to determine extent of the void and B&R to provide a repair procedure.
b.
B&R Engineering Change Method (ECM) 3428 which,rovided the required repair procedure.
c.
UESC Inspection Report No. 5-3041 for inspection of the void.
d.
UE&C ispection Report No. 5-3065 - witnessing grouting , of the void in accordance with ECM 3428, described it as ] satisfactorily filled and reported that grout test cubes
had been cade.
Thin. item is resolved.
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. . . - ,. . . . . ~- TELECO % EE) lei []Pd October 11, 1977 LOWEU. E. RCE v.a am.... '"'"" c o..~ a. Serial No. 391 14191 259-5242 Docket No. 50-346 gAli!6/ f' .,? ' n. 4 , ' MtC$1l[] ' y NC'/ 9 j Mr. Ja:es,.3 [_a; u,y, gg.dd"c4 I L4 Regional Director, Region III !A Sou ~ cry 9j Office of Inspection & Enforce =ent
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