IR 05000320/1976004
| ML19220B204 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/05/1976 |
| From: | Folsom S, Heishman R, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19220B192 | List: |
| References | |
| 50-320-76-04, 50-320-76-4, NUDOCS 7904250507 | |
| Download: ML19220B204 (13) | |
Text
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IE:I Form 12 n 75) (Rcv) Q[ 4,
4g%gs - . %[[%q, % U. S. NUCLEAR REGULATORY CC'!:iISSION s g 017 ICE OF INSPECTIO i CD E iFORCCiEh7 .
REGION I
. . IE Inspection Report No: sn_,en/7A_nt Docket No: 50-320 ' ic ensee: Metrocolitan Edison Cocoanv License No: CPPR-66 . Box 542 Priority: _ Re,a<,7 v o o r, e. 1..,,4, lonna Category: A Safeguards Group: - Location: Middletown, Penna.
(MI-2 ) Tvoe of Licensce: ' PWR 959 MWe (B&W) ' Routine - Unannounceo Type of Inspection: Dates of Inspection: v.x,-,,,-. ,,_,a lo7c Dates of Previous Inspection: January 27-30. 1976 , = ks ej".l f.?fl W \\ ..l < '#-N # #
. ' "" " Reporting Inspector: L.
DATE f.Y,s{s. Narrow,ReactorInspector /lo _! f ",5 L' { ,- " #' ' *' # ' ' ' -
' ' ' ' " Acco=panying It:epact.srs: S. Folsom, Reactor Inspector DATE & W Y DATE DATE None Other Accc=panying Personnel: f a,- Y* OfE $ y e
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J-77M- ' Y-* [. ?', ' L cted By:
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R. F. Beishcan, Coostruction Proj ect Se,ction-Chief " 'g'l}~ C [' g6Q - ~
- - . SUMMARY OF FINDINGS ~ Enforcement Action _= A.
Items of Nonce =oliance ? None.
Licensee Action on Previously Identified Enforce =ent Ite=s I.omplete documentation for hangers BSH 88 and 89 and spool piece 2-DH-124 has been resolved.
(Details, Paragraph 10).
Desien Changes . None.
Unusual Occurrences None.
Other Significant Findines A.
Current Findings
1.
Acceptable Items I
a.
Nondestructive examination of reactor cooling and dscay heat-piping installation.
(Details, Paragraph 2). b.
Instrumentation work in progress including equipment storage, l calibration and installation.
(Details, Paragraph 3). c.
Instrumentation documentation including vendor sueveillance, receiving inspection and storage and calibration.
(Details, Paragraph 4).
2.
Unresolved Items None.
B.
Previousiv Reported Unresolved Items The following ite=s have been resolved: 1.
Replacement of defective Westinghouse W-2 switches.
(Details, Paragraph 5).
2.
Motor Control Centers OdCC's) i= properly wired with GE Vulkene l "600" cable have been rewired.
(Details, Paragraph 6).
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_2_ _ 3.
Testing of hydraulic restraints will be in accordance with Technical Specifications.
(Details, Paragraph 7).
4.
Procedures have been revised to provide instructions for ' tightening anchor bolts.
(Details, Paragraph 8). 5.
Criteria for alignment of piping is provided by sketches of joint align =ent.
(Details, Paragraph 9).
C.
Deviations . None.
Exit Interview An exit interview was held at the site on February 25, 1976.
i Persons Present General Public Utilities Service Corcoration R. F. Fenti QA Auditor S. Levin, Project Engineer P Levine, QA Auditor .sashy, QA Engineer i
.. Stromberg, Sr. Site Auditor J. E. Wright, Site QA Manager United Engineers and Constructors J. Carrabba, Field Supervisor QC V. E. Cichocki, Construction /QC Coordinator Superintendent D. C. Lambert, Field Supervisor QC . Burns & Roe , W. P. Dornsife, Project Engineer G. T. Hrrper, Site Project Engineer F. X. Findar, Lead QA Engineer The items discussed are sunmarized below.
In each case, the licensee acknowledged the information.
A.
Scope of Inspection The inspector stated that the inspection was conducted to review the k status of outstanding items and the QC program for safety related instrumentation and piping.
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- - . _3_ _ . B.
Items of Noneccoliance and Unresolved Items {. The inspector stated that no ite=s of noncompliance or unresolved ' ite=s had been identified during this inspection.
j . C.
Acceptable items The inspector identified the items listed under Cutvent Findings of the Su==ary of Findings and stated that these items :ad been inspected with no discrepancies identified.
(Details, Paragraphs 2, 3, & 4). D.
Pryviousiv Reoorted Items The inspector discussed the items listed under Previously Reported Unresolved Ite=s of the Su--ary of Findings and stated that these itens are re. solved.
(Details, Paragraphs 5, 6, 7, 8 & 9).
E.
Previousiv Identified Enforcement Iteq The inspector later called the lice-.ee's representative and infor=ed him that the previously identified nonce =pliance concerning inec=plete vendor documentation for piping and hangers had been resolved. (Details, Paragraph 10).
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- - . DETAILS
3 1.
Persons Contacted Cencral Public Ur411 ties Service Corporation R. /. Fenti, Qutli'.y Assurance Auditor S. Levin, Project Engineer ' P. A. Levinc, QA Auditor G. L. Roshy, Quality Assurance Engineer J. E. Spinak, Lead QA Engineer J. Stromberg, Site Quality Assurance Auditor J. E. Wright, Quality Assurance Manager United Engineers and Constructors A. J. Ca=pbell, QC Engineer, Instru=ents R. Crofton, Welding Engineer R. Dourte, Asst. QC Supervisor K. Harvey, QC Engineer, Instru=ents . D. Lambert, QC Supervisor F. W. Martin, QC Engineer, Instruments F. Mikolaj czyk, Ins'trument Supervisor J. C. Rebox, QC Engineer, Receiving E. Somdahl, Instrument Supervisor Babcock and Wilcox R. Kunz, QC Supervisor J. Downey, Site Supervisor, Industrial Inspection 2.
NDE of Pining Installation The inspector reviewed NDE requirements and records of field instal-lation of reactor coolant pipe spool A-51-1 and decay heat system pipe spool 2DH-135.
Item A-51-1 was installed by B 6 W Construction Company (B&W) in accordance with their Field Co,struction Procedure (FCP) No. 9 and drawings 141562, 141563 and F5i 4.
Joints WJ-2-2 and WJ-5-2 were velded and inspected in accordance with FCP 9 and QC procedure 9A-124/C-6.
In addition to signatures of the inspectors on FCP 9 designating perfor=ance of the designated operations, reports of dimensional inspections were on file.
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Calibration records of test equip =ent and qualification records of NDE personnel were examined and deter =ined to be in compliance with - the appropriate procedures.
k'elding of Joint 2DH-135A was performed by United Engineers with NDE by Conam Inspection, Inc.
NDE included PT and visual exa=- ination of the root pass and PT, RT and visual examination of the final veld. UESC Form 7005 dated Dece=be-3,1974 was examined and these examinations had been performed and initialed by showed that inspectors whose qualification records showed them to be properly quellified.
The inspector also examined Radiographic Inspection Report IR-1 dated February 21, 1973 which showed all X-rays to be accep'cio le.
Perfornauce of prescribed NDE activities conformed to the requirements of th e applicable procedures and Table 3.2-1 of the FSAR with no discrer3ncies identified.
3.
k'ork ir, Proeress - Instrumertation , The inspector examined the following instrumentation activities: a.
Ecuie=ent Storage Instru=ents and components were stored in a warehouse adjacent to the UESC Instru=ent Shop.
Temperature and hu=idity were controlled and periodically checked.
Specified limits were 40-110 F, and 70% maximum humidity.
Nonconforming instruments and components were hold-tagged, logged, and stored in cabinets separated from conforming equipment.
(a) A report of equipment in hold status was issuad bi-weekly to insure resolution.
The latest report showed no ite=s on hold status for = ore than 3 months.
Quality control inspection reports covering identity, shipping da= age, and documentation had been prepared for all instrumen-tation received.
(b) Instrvrent Calibration The inspector witnessed the bench calibration of Foxboro Low Range Reactor Coolant Pressure Transmitter No. RC-3A-PT5, Model No. El:GM Serial No. 2517291.
The work was performed
' - by the UE&C instrument mechanics and was witnessed by an M ' C _IO . l _ e
_ _ _ -6- . i Instrumentation QC Engineer.
The test equipment consisted of a Foxboro Current Calibrator, Model 8121A and a Heise Pressure Gauge. 0-3000 psig.
Both instruments had been ' calibrated recently.
The calibration records, and trace-ability to the National Bureau of Standards, were examined by the inspector.
The transmitter calibration was performed in accordance with Foxboro Instru=ent Book No. 1934 and the UELC calibration procedure.
The instrument was sequentially calibrated at 0, 100%, 75%, 50% 25% and O.
The as-found readings were all within the stated tolerances, and no adjustments were required.
(c) Instrument Installations The inspector examined co=pleted work and work in progress on the installation of instru=ents and components in the Reactor Protection System, Engineered Safety Feature Actua-tion System, and Plant Control System.
This included level, pressure, and temperature sensors; instrument racks, panels, , actuating devices, lines and conduits in the containment building, auxiliary building, and control room.
The following is a partial listing of the instru=ents exam- ' ined: RC-2A-PT1 Reactor Coolant Pressure Transmitter (hold-tagged due to response time - found in argineering review) RC-14A-PTl Keactor Coolant Flow Transmitter RC-14B-PT1 Reactor Coolant Flow Transmitter RC-1-LT-1 Pressurizer Level Transmitter RC-1-LT-2 Pressurizer Level Transmitter SP-6A-PT2 Steam Generator Outlet Pressure Transmitter SP-6B-PT2 Steam Generator Outlet Pressure Transmitter MU-DPT-3836 Diff erential Pressure Indicator SP6A-PT1 Steam Generator Outlet Pressure Transmitter SP63-PTl Steam Generator Outlet Pressure Transmitter RC-1-LT3 Pressurizar Level Transmitter SP-1A-LT3 Operating Steam Generator Level Transmitter RC-22 PT4 RC Pu=p Seal Cavity Pressure Transmitter SP-1B-LT5 Startup Steam Generator Level Transmitter MUdPT-3836 Makeup System Differential Pressure Transmittet ( - h l . - l - . ,
_ - -7- . s The instru=ents and related components were examined for confor=ance to drawing and specification requirements for , identification (including color coding), location, anchoring, supports, =ounting, protecting, and physical separation from redundant instru=ents and high pressure piping.
The inspector exa=ined vor'. in progress on the vall =ounting . and tubing of MUdPT 3836.
All tube ends and instru=ent openings were found to be plugged except where connection work was in progress.
The place =ent, =ounting and anchoring were found to confor= to the construction drawing require- =ents.
Protection fro = adjacent construction operations was found to be inadequate at sete instru=ent locations.
This was corrected during the inspection by the erection of plywood and woven-vire panels around the instru=entat: ion equipment.
No discrepancies were identified with respect to instrument work in progress.
4.
Instru=entation Docu=entation The following docu=entation was examined during the inspection: a.
Vendor Surveillance (1) GPUSC QA Vendor Surveillance Report, January 27, 1975, at Mercury Cc=pany, Norwood, Mass.
Instru=ent Racks 425, 466, 436, 437, 439 vere inspected, docu=entation reviewed, and tests vitnessed prior to shipping release.
(2) Mercury Co=pany Form NFP-1."
Data Report for Fabricated Nuclear Piping Subasse=blies, Dece=ber 2,1974.
b.
Receipt Insnection and Storare (1) UE&C Bi-k'eekly Hold Tag Log Simary, January 27, 1976, signed by GFUSC QA Manager, which listed tag nu=ber, date issued, vender, ite=, reason for hold, conditional release authori-zations, and cogninant engineer.
(2) Eurns & Roe Instru=ent Status List - February 13, 1976.
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Instrument Calibration (1) Co=monwealth of Pennsylvania Bureau of Standard, Weights, , and Measures, August 15, 1974 Test No. PA74193 " Report of Test for Mars Standards."
(2) Foxbeco Instruction Book No'. 1934 for Model ti?GM Transmitter.
- (3) UE6C Instru=ent Calibration Data Sheet, Instrument No.
NS-PI-526, Nuclear Service Closed Cooling, Panel and Control Room, January 27, 1976.
(4) UE&C Procedure MCP-13-2, Rev. 1, " Bench Test of Plant Instrumentation and Checklist."
, (5) GPUSC QA Audit Report 76-01 December 18, 1975.
(6) GPUSC QA Audit Report 75-08, B&W Calibration Control Program, February 10, 1975.
(7) UE&C QC Procedure QC-13-2, Rev. 5 " Tool, Gauge, and Instrument Controls", August 9, 1974.
(8) UE&C Cene.ral Construction Procedure GCP-1-2, Rev. 32, Novc=ber 13, 1975 " Drawing, Specification and Document Control".
d.
Instrument Installation (1) Mercury Company Drawing NPC-3398-612 Rev. 2 April 22, 1974; specifying Seismic I mounting.
(2) UELC QC Inspection Report for Rock #424, November 18, 1975.
(3) UE&C Engineering Change Me=oranda 2822 and 2508.
(4) UE&C Procedure ECP-lO-2, Rev. 3, " Instrumentation Insuall-ation".
(5) UE&C QC " Checklist for Place =ent and Anchoring of Items Under Scope of ECP-10-2.
(6) GPUSC QA Audit Report 75-07, January 23, 1975.
( No discrepancies were identified.
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Westingbouse W-2 Switches [- I & E (Formerly DRO) Bulletin 74-6 had identified a possible safety p , problem in the use of Westinghouse W-2 switches and requested ' d .information from the licensee concerning use of these switches an corrective actions to be taken.
13, 1974 the licensee stated that two By letter dated September such switches had been installed in the Diesel Generator circuitry and would be replaced.
The inspector examined a certification from Beloit Power Systems Incorporated 10, 1975 dated Nove=her the Emergency Generator Control Panels had been which states that modified with the kit of parts supplied by Westinghouse for this purpose.
This item is resolved.
I= proper Wirine - GE Motor Control Centers 6.
1 & E (For=erly DRO) Bulletin 74-13 had reported a deficiency in termination of GE Vulkene "600" cables in certain 480V motor control centers and requested information from the licensee con-cerning possible deficiencies of this nature and corrective actions By letter dated Dece=ber 24, 1974 the licensee if necessary.
identified the equipment using this type of cable, stated thar a visual inspection and pre-operational testing of this equipment would be performed, deficient terminations would be corrected and the units tested for acceptance during pre-operational testing.
The inspector examined the following documents: GPU me=orandum stating that all 82 safety related 480V MCC's had been examined and that i= proper terminations were identified a.
in 52 breakers, Meeting notes dated June 11, 1975 which concluded that GE will b.
provide supervision, materials and cri= ping tools and UE&C This work will provide craftsmen for this cable replacement.
to be performed at the site.
Letter dated June 25, 1975 with attached instructions for c.
reviring of MCC's.
d.
Letter dated January 14, 1976 from GE advising of rewiring of MCC's identifying them by nu=ber.
( Testing of the units will be performed as a part of the pre- ' operationsl testing.
Ug} - p * 7 ' ' - l This iten is resolved.
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_ - . -10- _ = 7.
Hydraulic Restraint Systems . . IE Bulletin 75-05 had advised licensees of certain proble=s which k had been encountered with hydraulic restraints and requested information concerning testing and surveillance programs for these units.
By letter dated June 20, 1975 the licensee identified four such units and provided the information requested.
Subsequently, a surveillance program has been incorporated into the Technical Specifications.
This item is resolved.
8.
Diesel Generator (D-G) Anchor Bolts During a previous inspection of the D-G the inspector had observed that specific instructions for tightening of anchor bolts were not available.
(Ir.spection Report 75-13).
The inspector examined UE&C Nuclear Construction Procedure NCP-13-2 Rev. 3 dated February 9, 1976 " Unloading and Installation of the Diesel Generator".
Part 8.0 of this procedure provides specific instructions for tightening these bolts and Attach =ent "B" provides the torque values for various sizes and types of bolts.
The inspector was infor=ed that similar instructions had been provided for installation of other anchor bolts as well.
This item is resolved.
' 9.
Mis-Alignment of Pipinst During a previous inspection, mis-align =ent of piping at joint 2-DH-128 and lack of acceptance criteria for alignment of piping at joints had been identified as an unresolved item.
(Inspection Report 75-14).
The inspector examined the following documentation: a.
M. W. Kellogg (MWK) Isometric 2-8-23 Rev. 1/A which had been approved by the A-E and which showed an angle of 1 48' at joint 2-DH-128.
b.
B & R Drawing 2077 Rev. 5, attachments 4 and 5 butt weld alignment tolerances.
k.
74 CB - , . . .
, - - -11- . the Discussion with the B & R Site Project Engineer established that dimensional tolerance shown for the fit up gap controls the align =ent ' Cold springing of pipe is controlled by of piping at the joints.
2555-64, Section 3.5.4 of specification 2555-64 provi.is . specificationall Engineers Dimensional Drawings will indicate the particular that The inspector examined piping system cold spring requirements.
di=ensioned drawings for MSL, feedwater, nuclear service river water notes on cold springing of and relief valve piping and noted that piping were shown on those drawings.
This item is resolved.
10. Vendor Documentation _ Incomplete vendor documentation for pipe hangers BSH88 and 89 and for spool piece 2-DH-124 had previously been identified as a non-compliance (Inspection Report 75-14).
By letter dated February 13, the " Certification and Release for 1976, the licensee claimed that together with Packing List 165-W provided the necessary Ship =ent" the approval of the documentation for hangers BSH88 and 89 and that QC Inspector on drawings F-509 and F523 constituted certification of conformance for pipe spool 2-DH-124.
The inspector discussed these questions with the licensee's repre-sentatives and examined the documents previously identified as well as other documents available on site, all as shown below: Hangers BSH88 and 89 a.
The inspector stated that as previously reported Packing List Review of this list 165-W had not been available for review.
included the lugs for hangers BSH88 and 89 but showed that it did not include the hangers themselves.
The inspector then 27, 1972 reviewed a Certificate of Compliance dated September f rom Crawford Manuf acturing Company for hangers BSH-45 to BSH-91.
No discrepancies were identified.
b.
Socol Piece 2-DH-124 5, Section The inspector examined UE&C Procedure QC-4-2 Rev.
the documentation sub-IV.5 of this procedure provides that the vendors plant mitted to the Quality Assurance Engineer at shall be reviewed for confor=ance to the applicable codes and specification require =ents as identified in the purchase order the QA Engineer shall stamp, date and sign the and also that documentution upon satisfactory completion of the review.
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The inspector also examined Paragraph 6.2.2 of B & RDivision 2 "We - {
2555-64 - ~ ~ specificationThis Paragraph states,'in part " Contractor shall Testing".
and traceable to caintain records of all information pertinent the fabrication and testing of detail caterial and f abri-procedures Records shall include nondestructive test and qualifications, records of acceptance tests and radio-cations.
graphs. A su==ary list and copies of the above records shall be submitted to Construction Manager upon shipsent of each individus1 spool piece to the site.
After review of this information at Region 1 Office it was decided that: The citation for lack of cocplete vendor documentation for hangers BSH88 and 89 is withdrawn since the certification a.
examined during this inspection was available on site prior to release of the hangers for construction.
The approval sta=p and signature on drawing F-509 will be b.
accepted as confir=ation of review of Quality, The lack of vidigage measure =ents on site prior to release of is considered to be in noncompliance with c.
item 2-04-124 10 CFR30, Appendix B, Criterion VIII, since it is contrary to 2555-64.
the requirements of specification . This item is resolved since the vidigage measurements were furnished to the site and examined by the insp2ctor prior to conclusion of inspection 75-14.
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