IR 05000387/1980033
| ML17138B827 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/05/1981 |
| From: | Mattia J, Mcbrearty R, Narrow L, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B826 | List: |
| References | |
| 50-387-80-33, 50-388-80-20, NUDOCS 8103050812 | |
| Download: ML17138B827 (17) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-387/80-33 Report No.
50-388/80-20 50-387 Docket No.
CPPR-101 t
d Licensee:
Priority B
Category 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name:
Susquehanna Units 1 and
Inspection at Berwick, Pennsyl vani a Inspection condu ted:
Dec er 1 - ll, 1980 Inspectors Approved by:
L. Narrow, Reactor Inspector g Ci gc.
c rearty, e
or nspector R.. Paolino, Reactor Inspector a
ia, c ing ie, rogec s Section RC8 ES Branch zffl d
s>
ned date signed (- u5-8 date signed
.
date
'gned Ins ection Summar:
Unit No.
Ins ection on December l-ll 1980 Re ort No. 50-387/80-33 reas ns ecte
outsne unannounce snspectlon y t ree regsona ase inspectors
.
of icensee s work and gC activities related to installation of instrumentation systems, performance of the preservice inspection and previously identified items.
The inspection involved 80 inspector hours on site.
Results:
No items of noncompliance were identified.
7Unst No.
Ins ection on'December'1-11, 1980 (Re ort No. 50-388/80-20
~A'<<d:
t dt b
t by dt tb dt b t of the licensee's work and gC activities related to installation of instrumentation systems and previously identified items.
The inspection involved 17 inspector hours on site.
esults:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
sx03060
'. DETAILS Persons Contacted-Penns lvania Power and Li ht Com an R. A. Beckley, Coordinator, NDE Training and Program P; 0: Capotosto, Electrical NgA Engineer E.
W. Carroll, Senior NgA Analyst
.
A; Cassel, Resident Engineer
"S. L.: Qenson, Project Construction Manager
"R., H. Featenby, Assistant Project Director R.'. Harris, Licensing Engineer (Allentown)
"P. Kyner, Resident N(A R..E.
Matthews, NgA Engineer R. J.
Prego, Electrical NgA Engineer
"A. R. Sabol, Manager, N(A
"H. E. Stokes, Project Construction Engineer F.
L. Wu'rst, Project Engineer, NQA (Allentown)
Bechtel A.
H.
R.
0.
R.
J.
L.
J.
R.
N.
"K.
J.
R.
0".
Bisesti, Assistant Project Manager Cranston, Resident Engineer E. Crowe,:Lead Electrical.,Engineer Donati, Electrical gC Supervisor A. Drucker, Lead gA Engineer Foussat, Resident Plant,Design Engineer Hershey, Lead I8C Resident Engineer Hydrick, Lead gC, Instrumentation H. Khandhar, gA Engineer O'ullivan, Assistant Project Field Engineer Rezek, Lead Instrument Engineer Snyder, Field Electrical Engineer Stout, Project Field gC Engineer Tutini, Lead Instrument Superintendent Warren, I8IE Superintendent
Yenson, Lead -Small Pipe Engineer General Electric Com an R. Hildebrand, Field Engineer R.
A. Hosier, I&SE.Site gC Supervisor A. Lileck, Construction Engineer 0.
K. Voget, UT Level II, Automated Examination System T. Young, Field Engineer
" denotes those persons present at the exit interview.
Other craftsmen and technicians were interviewed as necessary when the inspection interfaced with t;heir wor.
Plant Tour The inspector observed work activities in 'progress, completed work and plant status in several areas of the plant during a general inspection of Units '1 and 2.
The inspector examined work items for obvious defects-or noncompliance with NRC requirements or licensee commitments.
Particular note was taken regarding the presence of quality control inspectors and indications of,quality control activities.
In addition, the inspector interviewed craft and supervisory personnel encountered
'. in the work area.'.
During. the facility inspection the inspector observed that the small pi'pe (1 "in.=) instrument lines number SP-DCA-119-5 and number SP-DCA-118-4 from pipe taps in the Reactor Circulation Coolant Loop A cross each other.
The spacing at'the crossover point is less than 2 inches.
Loss of both
.of these lines would deprive the plant operator of information concerning flow in recirculation loop A.
The inspector could find no criteria on site applicable to separation of small bore pipe.
The 'inspector met with licensee representatives
'in an attempt to determine separation requirements for small pipe in general, and specifically.,for the fl'ow instrumentation lines referred to above.
This matter could not be resolved on site and the licensee has written a letter (PL G-1615) to the NSSS supplier requesting that those require-ments be provided.
This item is unresolved pending resolution of this matter by the licensee and revi'ew by NRC.
(387/80-33-.01; 388/80-20-01)
Instrument Com onents/S stems Mork.Observations The inspector examined work performance, partially completed work and completed work pertaining to safety-related instruments to determine whether the requirements of appliqable specifications, work procedures, drawings and instructions have been met in areas relating to installation, routing, instrument type, range and si'ze.
Areas inspected for this determination include:
Drawing Nos. JD-27-6-1 revision 2, JD-27-6-lA revision 3, JD-27-6-1B revision 3, JD-27"1-1B revision 8, JD-27-1-1 revision 8 and JD-27-1-1A revision 8.
Instrument Panel Nos.
1C001 and 1C058.
Instrument Nos.
PI-E21-1R001A, PI-E21-1R001C, PI-E21-1R001B, PS-Ell"1N011B, PS"E11-1N011D, PS-E21-'1N007A and PS-E21-1N007B.
Core Spray System No.
151.- Specification Nos.
8856-E-53,, 8856-ZE-53, 8856-C-72,.8856-J-G16.
No items of noncompliance were identified.
4.
Instrum'ent Com onents/S stem ualit Record Review A.
. The'inspector reviewed pertinent work and quality records of safety-related equipment to determine whether the records reflect work accomplishments consistent with NRC requirements and licensee commitments in the areas of receipt inspection, material qualifica-
- tion and procurement.
'reas examined for this determination include the following items:
,, Material Receiving Report Nos.
GER-289, GER-710 and GER"653.
Purchase Order Nos.
PAL M-1 and PP8L M-l-AC.
.,'pecification 8856-M-l.
Drawing Nos.
169C8278G001, 164C5359P001 and 169C8269G001.
Certificate of Conformance dated March 7, 1979, March 10, 1977
--and July 25, 1979.,
No items of noncompliance were identified.
B.
The inspector reviewed the following licensee/contractor nonconformance reports relative to cable, terminations and related equipment to
. determine, whether the records are curren't, legible, complete and readily. retrievable.
Nonconformance reports examined include:
No NCR ¹6841 and ¹6845 pertaining to cable supports.
NCR ¹6838 pertain'ing to cable separation.
NCR ¹6815 pertaining to color coding of PGCC and ACR panel.
NCR ¹6812 pertaining to routing of GE cable in ACR/PGCC panel.
NCR ¹6807 pertaining to damaged cable.
NCR ¹6804 pertaining to raceway/conduit separation.
NCR ¹6745 pertaining to incorrect identification of 4 cable reels.
NCR ¹6739 pertaining to cable separation in control panels.
NCR ¹6720 pertaining to missing cabl'e qualification data.
.
NCR ¹6712 pertaining to raceway/conduit separation.
items of noncompliance were identifie.
Ultrasonic Examination of Reactor Pressure Vessel RPV Melds General Electric Company (G.E.),was contrycted by the licensee to perform the preservice volumetric (ASNE Section XJexaminations= of the applicable RPV welds.
The required examinations are currently being done using the G.E.
Remote/Automatic Ultrasonic Examination System.
The system is made up of an ultrasonic instrumentation s'ubsystem, a
data processing subsystem and two ultrasonic scanners (vessel scanner and nozzle scanner)
which are controlled by a minicomputer.
The scanning vehicle is held to the'outside vessel wall by four sets of magnetic wheels.
Three redundant guidance systems are utilized to assure that the operator is aware of the position of the scannner.
The inspector reviewed procedures, NDE personnel certification records, equipment calibration and certification records and witnessed,a portion of the ultrasonic examination of RPV circumferential weld.number AO.
The following procedures were included in the inspector's review:
Procedure No. ISE-(AI-329, Revision 1, "Remote Ultrasonic Examina-tion Procedure (Vessel)"
Procedure No. ISE-(AI-330, Revision 1, "Remote Ultrasonic Examination Procedure (Nozzles)"
'Procedure No.
21A3815AA, "Evaluation of Ultrasonic Indications in
,Reactor Pressure Vessel Circumferential and Longitudinal Melds and Base Metal" Procedure No.
386HA480, "Certification of Nondestructive Test Personnel" The procedures delineated applicable welds, required examination equipment, calibration techniques, beatg angles, examination frequency and the material
'thickness range to which they are applicable.
System calibration is established using calibration block, S/N 1, heat number, B-5083"1 which 'contains both notch and drilled hole calibration reflectors.
The frequency of calibration is governed by Code Case N 234 and N 235.
The Code Cases permit a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> between calibration checks and their use is approved by the NRC.
The examination personnel were found to be properly certified and the equipment was being used within the current calibration period.
No items of noncompliance were identifie.
Preservice Ins ection Data Review The inspector selected PSI data generated by NES for review to ascertain compliance with ASME Code and regulatory requirements.
P Data sheets associated with the ultrasonic examination of the following welds were reviewed:
Residual Heat Removal RHR S stem Melds Meld No. GBB-106-1-6-C Meld No.
GBB"106-1-FM2 Meld No. GBB-106"1-FM4 Meld No.. GBB-105-1-1-O Recirculation S stem Welds Meld No. VRR-B31-2-FMB Meld No. YRR-B31-2-2-S Meld No.. VRR-B31-2"2"A Meld No. VRR-B31-2-2-T Weld No. YRR"B31"2-2"R Meld No. VRR-B31"2-3-M The data were considered. with respect to system calibration, equipment identification, procedure identification, examination frequency, beam angle, extent and limitation of examination, evaluation of results and examination personnel identification.
No items of noncompliance were identified.
7.
Review of Nonroutine Events Re orted b
the Licensee
.By letter dated March 2, 1979 the licensee reported, as a significant deficiency in accordance with 10 CFR 50.55(d),.ailure of valve manufacturers to stake the stem nuts fastening certain Limitorque motor operators to valves (79-00-02).
This item had been inspected during Inspections 387/80-15; 387/80-10 and 387/80-19;,388/80-13 but remained unresolved pending completion of staking or tagging all nonconforming valves.
The inspector discussed staking of the valves with the responsible field engineer and gC inspector and reviewed the following documents:
NCR No.
3424 which had been dispositioned and closed by gC acceptance on November 26, 1980.
Computer printout of valves showing inspectors'otes of inspections
'nd'taking.
MCAR G-1 and the final report of this corrective action request.
The records showed that all g-listed valves which required staking had been inspected and either staked or found to have been previously staked.
In addition, the valve suppliers had been informed of the potential problem to assure that valves would be staked on any future orders, and procurement gC had been instructed to inspect all rising stem operated valves for proper staking.
The inspector had no further questions concerning this item.
By letter dated May 7, 1979 the licensee reported, as a significant deficiency in accordance with 10 CFR 50.55(e),. abnormal wear in the surface of the roller pin in a corsehead assembly of the emergency diesel generator (79-00-04),
This deficfency had also, been reported by the vendor, Cooper Bessemer Company (C-B) in accordance with 10 CFR 21.
The inspector examined the following records:
NCR No.
3852 which had been dispositioned to perform the rework and replacement as directed by a C-B representative and which showed the work to have been performed and accepted for the four engines.
The gC Inspection Record (gCIR) No.'24.0-M-30-06.501-7 showing inspec-tion of the rework and replacement.
Letters from the CB service representative stating that he had supervised the changout of the crosshead assemblies,-
removal of Part No. Z25-1-2 810 and installation of Part No. 225"1-2 816 for each of the four engines.
This item is resolved.
By letter dated January 22, 1980 the licensee reported, as a potential significant deficiency in accordance with 10 CFR 50.55(e),
a deficiency in coping of structural steel beams.
(79-00-13)
This condition had previously been identified during NRC inspection 50-387/79-28; 50-388/79-15.
Following analysis and evaluation of the problem, the licensee reported, by letter dated July 14, 1980, that the nonconforming conditions could not have adversely affected safe oper-ation of the plant and was therefore not reportable in accordance with
CFR 50.55(e).
Nevertheless, corrective and preventive actions have been taken in response to the findings of the NRC inspection reports identified above and are described in NRC Inspection Reports 50-387/80-21; 50-388/80-14 and in Paragraph 10 of this repor The i'nspector had no further. questions concerning this item.
By letter dated March 23, 1979, the licensee reported, as a potentially significant deficiency in accordance with 10 CFR 50.55(e),
defective diodes in Circle Seal Model J-69B solenoid valves (79-00-03).
Following evaluation and analysis of the impact of the valves on safe operation of the plant the licensee determined and reported that the deficiency was not reportable in accordance with 10 CFR 50.55(e)..
The present approved design does not use these solenoid valves in any location where their failure could affect safe operations or shutdown of the plant.
However, in view of the possibility that future changes might result in use of the valves in locations which might affect safety of operations or shutdown, the licensee decided to return all such valves to the vendor for replacement of the diodes.
The inspector examined the following documents:
MCAR 1-31.
The final report dated August 2, 1979 concluded that the present design includes no Circle Seal Solenoid Valves whose failure would disable a safety system but valves purchased for spares might in the future be used in a safety system.
Bechtel TMX EMG-3711 which identified forty Circle Seal Solenoid Valves for return.
NCR 3579 which identified the above forty valves for return to the vendor for replacement of diodes and which was closed on August 20, 1980.
Shipping Notice 8856-5684 recording return of the valves to the vendor.
Ouring review of MCAR 1-31 the inspector noted that seventy-seven of these solenoid valves had been furnished to equipment suppliers for installation on equipment such as was furnished to the site.
This item remains unresolved pending determination by the licensee whether the additional thirty-seven valves had been sent to the site and if so their present location and disposition.
8.
Licensee Action on NRC Bulletins Bulletin 78-12:
Atypical Material in Reactor Pressure Vessel Melds.
The reacto~ pressure vessel fabricator, Chicago Bridge and Iron Company, had submitted a generic report providing the requested information.
The weld material used was found to meet the applicable acceptance criteria as evidenced by NRC Memorandum dated July 10, 1980.
This items is resolve Bulletin 79-03:
'Longitudinal Meld Defects in ASME SA-'312 Type 304,
,S/S pipe.
The'nspector examined information requested to be furnished by this Bulletin:
Bechtel letter 123209 dated August 5, 1980 states that there are
-
no ASME SA-312'doubleweld pipe or fittings in safety related systems which are subjected to design stress greater than 85K of code allowable.*
- G.E. letter GP-80-170 dated October'20, 1980 states that no SA-312 is in use in the GE specified systems at Susquehanna.
This item is resolved.
The following Bulletins were sent to the licensee for information only.
The inspector noted that they had been distributed to personnel to whom the information contained may be of value.
Bul.letin 79-05:
Nuclear Incident at Three Mile Island, Unit 2 Bulletin 79-06:
Review of Operational Errors and System Misalignments
. Identified During the Three Mile Island Incident These items a'e resolved.
'I Bulletin.79-,11,:.
Faulty Overcurr ent Trip Device in. Ci'rcuit Breakers For Engineered Safety Systems GE letter GB"79-162, dated July 6, 1979 and Bechtel letter 106328 dated July 3, 1979 both state that the type of circuit breakers identified in this Bulletin (Mestinghouse type DB-'50 and DB"75) are not used in safety related systems at this site.
This item is resolved.
Bulletin 79-04:
Incorrect Meights for Swing Check Valves Manufactured by Velan,Engineering Corporation Bechtel letter 108867, dated September 6', 1979, 'states that review of all plant design, mechanical and control systems, and field pur chase orders had been performed.
No Yelan swing check. valves were found to be used in safety related systems.
PP8L letter PLI 5061 states that Bechtel had been notified that should Velan swing check valves be installed in the future the concerns expressed in this bulletin 'are to be investigated.
Information was not made available to the inspector showing actions t'o be taken to assure that this request will be carried out.
This'tem remains unresolve Bulletin 80-02:
Inadequate guality Assurance for Nuclear Supplied Equipment GE letter GP-80-49, dated March 13, 1980, states that Marvin Engineering Company did not supply any of the equipment for the reactor feedwater spargers or thermal sleeves for this project.
This item is, resolved.
Bulletin 80"19:
Failure of Mercury-Wetted Relays in Reactor Protective
'Systems of Operating Power Plants Designed by Combustion Engineering Company PAL Memorandum PLl-9478 dated August 28, 1980 stated that the RPS for this plant was provided by General Electric Company and does not utilize the C.P.
Cl'are Mode HG2X-1011 mercury-wetted relays.
This item is resolved.
9.
Licensee Action on NRC Circulars Circular 78-18:
UL Fire Test This circular was furnished to the licensee for information and has been distributed to personnel to whom it may be of'interest.
This item is resolved.
The following circulars are closed based on documentation on file from
.Bechtel and General'lectric Company as well as the licensee's internal correspondence to the effect that none of the identified equipment was furnished for this project.
Circular 79"20:
Failure of GTE Sylvania Relay, Type PM Bulletin 7305, Catalog 5U12-11-AC with 120 v AC Coil Circular 79-23:
Motor Starters and Contactors Failed to Operate Circular 80-23:
Potential Defect in Beloit Power Systems Emergency Generators
'0.
Licensee Action on Previous Ins ection Findin s Closed Noncom liance 387/79-28-02.
88/79-15-01
Nonconforming coping of structural stee beams.
h1s tern has been reviewed during inspection 50-387/80-21; 50-388/80-14, and remained open pending completion and acceptance of work required by disposition of NCR 4288.
The inspector discussed work to be performed with the responsible field engineer and gA engineer and observed completed work and work in progress as required by disposition of this NCR.
Corrective work in Unit 1 had
been completed and repairs in accordance with drawing C"1187, sheet 2, are complete except for three beams which are identified on the drawing.
Mork on these beams is now i'n progress.
The inspector had no further questions and this item is considered to be resolved.
Closed)
Noncom liance 387/80-12-03
NDE personnel certification.
The inspector reviewed the following documentation relative to qualification for certification to Level II in the ultrasonic examination method of the Nuclear Energy Services (NES) employee in question:
Personnel certification record revised on July 9, October 17 and December 3, 1980 NES Inter Office Correspondence dated June 30, 1980 NES Inter Office Correspondence dated December 3,
1980 The above records state that the individual was given credit for 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> classroom instruction based on his completing the General Dynamics programmed instruction home study course in ultrasonic testing, and credit for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> classroom instruction which was provided by a ConAm Level II i'ndividual.
The aforementioned instruction is claimed for the period from May 1977 to May 1979 when the individual was employeed as a
UT trainee by ConAm Inspection.
The inspector stated that he had no further questions concerning this item.
Closed Unresolved Item 387/80-09-01
Preservice inspection program.
The inspector found that the NES gA Program Plan, document number 80A2767, Revision 6, approved by the licensee on October 23, 1980 provides licen-see control of the implementation of preservice examinations and program plan updating as examinations are completed.
The revised gA plan provides for PSI program Field Changes as needed, with tPe requirement that licensee approval be obtained prior to commencement of work on the changed item.
Provision is made to incorporate the Fie'ld Changes in the PSI program.
The 'above is intended to assure that updated system isometric drawings are incorporated in the PSI program on a timely basis and that the licensee exercise control over such changes as are necessary to maintain current drawings and records.
The inspector stated that he had no further questiqns concerning this item.
Closed Unresolved Item 50-387/80-06-03 and 50-388/80-04-03
Pertain-ing to vendor recommended inspection acceptance criteria for installation of compression fittings.
The inspector reviewed vendor data dated
May 16,* 1980 and witnessed tests conducted on site on December 9, 1980 to determine the effects of overtightening of compression fittings used with 0.065 wall stainless steel tubing (316).
The, tests indicate that overtightening (using.a 12, inch crescent wrench)
.is limited to 1 and 1/2 turns.
Vendor recommended installation is 1 and 1/4 turns, The inspector observed no reduction in tubing wall thickness when using the 1 and 1/2 turns, however there was a displacement of metal reducing the inside diameter of the tubing slightly at the point of contact with the compression fittings.
The inspector found. this acceptable.
This item is resolved.
Closed Noncom liance 50-387/80-12"01
Pertaining to the positive
>dent>ficatson,and segregation of gC documentation involving the computer printout.
The inspector reviewed the computer printout gT79R verifying that the licensee has modified his computer printout documentation of raceway nonconformances (NCR) to reflect current status.
The licensee has,added the letter E for raceways accepted prior the NCR and the letter N for raceways accepted after February 1979 and those raceways covered by NCR 2489.
Field Procedure No. 8856-E-2 addresses the computer printout procedure.
This item is.resolved.
Closed Noncom liance Item 50-387/79-36-02
Pertaining to the separation of redundant flow transmitters.
he inspector reviewed the nonconformance report (NCR) 4788 and verified the disposition by visual observation of
.completed work.
The l,icensee's action to preclude reoccurrence was found to be acceptable.
This item is resolved.
Closed Noncom liance* Item 50-387/80-19-01
Pertaining to cable tray softeners over sharp edges.
The inspector reviewed the licensee instruc-tions E-3. 0', section 3. 2 which requires tray softeners on all sharp edges and the Bechtel, interoffice memos dated July 24, 1980 from the Project Field Engineer and the Project Field guality Control Engineer requiring gC verification of tray softeners per Project guality Control Instructions (PgCI) E-4.0 and turnover re-verification per P(CI E-3.0 revised November 15, 1980.
This item is resolved.
Closed)
Unresolved Item 50-387/79-02-01 and 50-388/79-02-01:
Pertaining to the status of Bullet)ns and Csrculars on qualification of class lE
equipment.
This. item is being addressed by the licensee in his submittal (Volumes 1, 2 8'3 - Table 40.2-1) response to NRC question 040.2 on
-"Environmental gualification for Class lE Equipment."
The inspector had no further questions.
This item is closed.
Closed Unresolved Item 50-387/79-02-03 and 50-388/79-02-03
Pertain" sng to a 10 CFR 50.55 e
defic ency snvolvsng damage to winng and termination module connections for ACR equipment.
The licensee has instituted a 100K inspection program to replace all damaged/defective wiring.and terminations for the Unit
ACR equipment.
For the Unit 2 equipment, also on site, a similar program will be imposed should preliminary inspection show similar problems.
An inspection data sheet listing inspection criteria, results and correc-tive action is being issued for each cable/connector assembly.
The inspector had no 'further questions.
This item is closed.
Closed Noncom liance Item 50-387/79-36-01 and 50-'388/79-19-01
Pertaining to the snstallatlon of Class lE raceways conduit supports in concrete block walls of battery rooms.
The inspector reviewed NCR numbers 4801, 5108 and 5115.
NCR 4801 consists of 88 sheets listing disposition and corrective action based on analysis and load calculations for. each installation.
Licensee action 'to prevent re-occurrence appears adequate.
This item is closed.
0 en Unresolved Item 387/78-18-02
Inspection and acceptance of pspe supports to assure that threads of bolts are not in shear area.
The inspector examined the following documents:
guality Action Request (JAR) No. 8856-F-460 and response which states that (Field Change Request)
FCR-P-2004 has been issued and approved for criteria with regard to threads located in the bearing part of the shank.
FCR-P-2004 provides for revision to Specification M-213 as follows:
"The thread length in the load bearing area of the load study or bolt cannot exceed 1/2 the stock thickness of the clamp."
NCR 3343 for nonconforming conditions identified during inspection of pipe hangers including location of threads on studs and bolts.
This NCR had been closed out June 27, 1979.
The disposition included the statement,
"...gC is to perform a random inspection of stock three. bolt clamps in accor'dance with FCR-P-2005 to determine acceptance of Grinnell-supplied load studs or bolts.
Contingent
upon an acceptable inspection further final load bolt thread verifica-tions will not be requi,red, except to verify that load studs are centered.in the clamp."
Records were not available on site to establish that this random inspection has been performed nor to show the number of clamps examined during the inspection.
This item pema$ ns unresolved.
- 0 en) Unresolved Item 80-21-02
Melding of shear clip angles not in conformance with AMS Code.
he inspector discussed this question with the responsible gA and field engineering personnel.
Following identification of this'condition during inspection 80-21, the 1'icensee had inspected and identified additional clip angles in Unit 1 and had reported them on NCR No. 6386.
However, rework of the beam connections inside containment as required by NCR 4288 had resulted in no load being imposed on the clip angles, NCR No.
6386 had been dispositioned to "accept as is."
This items remains unresolved pending close out of NCR No. 6386.
0 en Unresolved Item 50-387/79-40-03 and 50-388/79-21-01
Pertaining to the sessmic qualsfscation and use of plastic tie wraps to support flexible metal conduit in the ACR/PGCC control panel.
The inspector reviewed the General Electric Company letter (GP-80-77)'in response to the licensee's letter (PLG-1346) dated April ll, 1980; Bechtel interoffice memo dated August 8, 1980 and nonconformance report No.
5361 for panels 1C611, 1C601 and 1C622.
The licensee fix for rigid mounting of the flexi-ble conduit prevented closure of the control console.
This item remains open pending acceptance of revised design for rigid mounting of.flexible conduit.
11.
Unresolved Items
\\
Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncom-pliance.
An unresolved item identified during the inspection is discussed in Paragraph 2.
12.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on December ll, 1980.
The inspector summariXed the purpose and scope of the inspection and identified the inspection finding a" i1/
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