IR 05000387/1980018
| ML17138B521 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/22/1980 |
| From: | Ebneter S, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B520 | List: |
| References | |
| 50-387-80-18, 50-388-80-12, NUDOCS 8010230043 | |
| Download: ML17138B521 (11) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
"50-387/80-18 R
p N
50-387 k
N CPPR-101 N
Priority Category Licensee:
Penns lvania Power 8 Li ht Com an 2 North Ninth Street Allentown Penns 1 vani a 18101 Facility Name:
Susquehanna Steam Electric Station, Units 1 and
Inspection at:
Berwick, Pennsyl vania Inspection conducted:
July 15-18, 21 and July 29-August 1, 1980 Inspectors:
R. Paolino, Reactor Inspector S.
D. Ebnet Chief, Engineering Support Section
RCSESB date igned date signed
. Approved by:
S.
D. Ebneter, Chief, Engineering Support Section 2,
RCSESB date signed agzzAi date signed Ins ection Summar
Combined Ins ection of Units 1 and'2 on Jul 15-
1980 Jul
1980 and Jul 29-u ust
1980 Combined IE Re ort No. 50- 87/80-18 and 50-388 80-12 Areas Ins ected:
Routine, unannounced facility inspection by a regional based inspector an supervisor of work activities pertaining to the installation of safety related instruments; review of previously identified inspection findings; review of licensee responses to IE Circulars/Bulletins; facility tour and discussions with craft personnel.
The inspection involved 78 inspection hours onsite by one regional based inspector and.;one supervisor.
Results:
No items of noncompliance were identified.
Region I Form 12 (Rev. April 77)
66XOa DETAILS Persons Contacted Penns lvania Power and Li ht Com an K.
W.
R.
AAR
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M.
P.
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- R J.
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Backenston, Project Engineer -
NPE Barberich, Nuclear Licensing Engineer Barrow, Stores Supervisor Beckley, Acting RN(AE Capotosto, gA Engineer Cassel, Lead. Resident Engineer Cheremjack, Assistant Electrical Repair Foreman Clymer, Senior NgA Analyst Coddington, Project Engineer - Nuclear Licensing Denson, Project Construction Manager Detamore, Operations Engineer Hendrickson, Manager - Licensing Kyner, Resident N(AE Lazarowitz, NPE Male, Assistant Manager - Nuclear Plant Engineer McVicker, Supervisor Engineer-NgA Prego, gAE Wetzel, Project Engineer - NgA Wurst, Project Engineer - NgA Sabol, Manager - N(A Schwan, Supervisor Engineer - NgA Skrocki, Parts Analyst Skoras, Engineer Level II Bechtel Power Cor oration
%*A N.
RAG R.
- AM K.
C Z.
RAW 5'A'
AAJ M.
J.
D.
Bisesti, Assistant Project Manager Covington, ISG - Coordinator Startup Engineer Cranston, Resident Project Engineer Crowe, Lead Electrical Drucker, Lead gAE Fetterman, Assistant Field Engineer Headrick, Assistant PFgC Incze, Lead Small Pipe Designer (S. F. )
Maurer, Supervisor Minor, Project Field Engineer O'ullivan, Assistant PFE Snyder, Assistant Lead Electrical I
Waddington, gC Engineer Yenson, Small Pipe Designer
U.S. Nuclear Re ulator Commission
- R. Gallo, Senior Resident Inspector
- Denotes personnel present at exit interview held at the Corporate Office in Allentown, Pennsylvania on July 21,'980.
I*Denotes personnel participating in exit'interview held at Allentown via intercom.
- Denotes personnel present at exit interview held on. site at Berwick, Pennsylvania on August 1, 1980.
2, 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 noncompliances with NRC requirements or licensee commitments.
Particular note was taken of the presence of qual,ity control inspectors and indications of quality control activities through visual evidence such as inspection records, material identification, nonconformance and acceptance tags.
In addition, the inspector interviewed craft and supervisor personnel encountered in the work areas.
No items of noncompliance were identified.
3.
Status of. Previousl Identified Ins ection Findin s
a.
Closed)
Unresolved Item 50-387 78-02-05 Pertaining to the.r'equirement for protection of cables from sharp edges in cable raceways.
An inspection of cable raceways by the Susquehanna Unit 1, NRC project inspector indicated several areas where damage to cables could occur from exposed sharp edges in raceways.
This unresolved item has been closed and upgraded.to an item of noncompliance in IE Report 50-387/80-16.
b.
Closed)
Unresolved Item 50-387 78-03-07 Pertaining to qualifications of cable splice procedure to LOCA environmen The inspector examined the following documents, BLP-11475, BLG-2227 and Specification E-135 determining that the licensee is using the LOCA qualified Raychem cable splice and procedure.
This item is closed.
c.
-
Closed Unresolved Item 50-387 79-26-01 Pertaining to cable failure when tested with AC voltage.
The inspector examined the General Electric test procedure TI-1644 which provides instructions for testing cable with AC voltage and for retesting with DC voltage upon failure of the AC test.
The inspector determined this to be acceptable.
This item is closed.
d.
Closed) Infraction 50-387 79-32-01 Pertaining to the installation of flow and level transmitters with expansion anchor bolt centerline measuring.
3 3/4 inches instead of 5 inches.
The inspector examined the following documents, PLA-436,and NRC 4771 which i.dentify cause, corrective action and action to preclude re-currence.
The inspector determined licensee action to be acceptable.
This item is closed.
e.
0 en) Infraction.50-387 79-36-01 50-388/79-19-01 Pertaining to seismic supports for Class IE raceways installed in block walls per drawing C-805 sh. 2 which did not require bolt spacing or minimum distance from through bolt to edge of block wall.
The inspector, examined licensee documents PLA-453 and NCR 4801 deter-mining licensee response to be acceptable, however rework of installation is incomplete.'icensee expects to complete this phase by September 3,,
3.980.
This item remains open pending NRC verifi'catidn of completion of rewor f.
0 en)- Infraction 50-387 79-36-02; 50-388 79-19-02 Pertaining to instrument tubing installation for redundant flow transmitters which did not meet separation criteria.
, The inspector examined licensee documents NCR 4788 and PLA-453 determining licensee response to be acceptable,
.however additional, work is required to correct tubing bends.
The licensee expects to complete this work by September 1,
1980.
This item remains open pending NRC verification of. work completion.
g.
0 en) Unresolved Item 50-387 79-40-03 50-388 79-21-01 Pertaining to the use of plastic tie wraps to support flexible conduit at the stationary benchboard end of control panel insert.
The licensee is awaiting vendor response to complete evaluation.
This item remains open.
h.
0 en Unresolved Item 50-387 79-40-05 50-388 79-21-03 Pertaining to Diesel engine testing to verify crosshead assembly pin modification.
The licensee stated that testing wi,ll be done during the pre-op test phase.
This item remains open pending NRC verification of testing.
0 en Unresolved Item 50-387 78-03-02 Pertaining to LOCA qualification testing of, Westinghouse Penetrations.
The'licensee has determined the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> LOCA qualification testing of November, 1979 to be inconclusive.
A nonconformance report (NCR 6187)
has been issued with instructions (EMC-5077) for retesting of two Westinghouse electrical penetrations.
This item. remains open pending NRC review of the full LOCA profile test result j.
0 en Potential
CFR 50.55(e Item 50-387 79-00-16 Pertaining to American Insulated Hire (AIH) cable defects; The licensee has determined that this item is not reportable.
Licensee document NCAR-1-42 identifies 12 cable deformaties discovered during the cable measuring and cutting operation.
NCR 4035 and NCR 4472 lists 28 cable reels of various size cable having 1 or more of 12 defects listed on MCAR-1-'42.
The licensee has taken cable samples with the above defects and pul.led them through conduit.
These samples have been sent to the manufacturer for testing in the LOCA environ-
'ment, This item remains open pending NRC review of licensee evaluation of test results and corrective action.
4.
Circulars and Bulletins a.
The inspector examined the following Circulars and Bull'etins to determine
,adequacy and acceptability of licensee response.
(1)
Items examined include:
IE Circulars 77-CI-13, 78-CI-08, 78-CI-13, 78-CI-16, 79-CI-02, 79-CI-05, 79-CI-17, and 79-CI-23 IE Bulletins 78-BU-02, 79-BU-11, 79-BU-25, and 79-BU-28 b.
The inspector determined. the licensee responses to be incomplete and not responsive to the NRC concerns.
.As an example:
IE Bulletin 79-BU-25 NRC Concern:
Failure of Westinghouse BFD/NBFD relays (listing specific NRC 'Recommended Licensee Action:
" Determine use of BFD/NBFD relays, 1 entify system where used.and provide written plans for test and replacement program, Licensee Action:
Licensee response to NRC (PLA-441) concludes no D
D re ays used at SSES in safety related systems, however a
check of the spare parts l.ist in the storeroom indicates a
BFD relay was on order on Purchase Order No. 500053, dated April 25, 1979 for use in safety related
KV switchgear.
The relay was located in storeroom Bin No. UU28,
Discussions by the inspector with licensee engineering and licensing personnel responsible for gathering data used in determining responses to 'IE Circulars/Bulletins appears 'to indicate that a minimal effort is made in obtaining and verifying data, used.
Backup documentation was not available for responses made to IE Circulars/Bulletins examined.
The licensee has stated that they are in the process of reviewing the procedure for responding to IE Circulars/ Bulletins.
A draft copy of the procedure will be'ready in two weeks and implementation is expected to occur by September 1,
1980, This item is unresolved pending NRC review of licensee's revised procedure f'r responding to IE Circulars/Bulletins and, implementation thereof.
(50-387/80-18-01; 50-388/80-12-01)
5, 'nstrument Com onents S stems - Work Observations The inspector examined work performance, partially completed work and completed work pertaining to safety related instrumentation to determine whether NRC requirements or licensee SAR coranitments are accomplished in accordance with applicable specification procedures, drawings and instructions.
For this determination the inspector examined the containment atmosphere radiation monitor sampling lines for monitor 1C227A/1C227B.
The inspector verified that the sampling lines conform to drawing nos.
SP-HCB-139-1, Revision 2; SP-HCB-139-2, Revision 1; SP-HCB-M78-6, Revision 4; and SP-HCB-122-1, Revision 3.
However, the inspector observed that the drawings did not reference nor incorporate the recomnended design requirements noted in ANSI N13. 1-1969 for obtaining a representative sample.
Section 11.5; 1.2 of, the FSAR lists Regulatory Guide 1.21 as the design criteria for the process and effluent monitors.
The Regulatory Guide 1.21 references the ANSI N33.1-1969 gui.de as an acceptable design criteria for sampling particulates.
The Regulatory Guide 1.21, paragraph 6 states in
. part that "A sample should be representative of the bulk stream or effluent from which it is taken.
Provisions should be made to assure that representative samples are obtained from well mixed streams or volumes by selection of proper sampling equipment--points--procedures.
The general principals for
. obtaining valid samples--are contained in ANSI NJ3. 1-1979".
The, ANSI document identifies methods for obtaining a representative sample through proper design and installation criteria.
The ANSI document discusses the effects of right angle bends, elbows, fittings and voids which can result in particulate losses (75K or more at each right angle bend)
when subiected to sudden changes in flow direction.
Voids (caused by the 1/16 inch pull-back on socket fitting welds) in the sample line which can entrap particulates that can be released at a later date due to line vibrations result in erroneous readings or reactor trip on high radiation.
Line slope is also addressed because of the need to keep the particulates in the flow stream
e so that a'representative sample reaches the monitor.
This is accomplished by sloping the lines downward to the monitor and taking advantage of gravity flow to prevent fall out of heavier particles.
The inspector observed that the sample lines referenced above and installed per the referenced drawings consist of 90o elbow fittings, tee's and voids at each socket weld fitting.
Discussions with licensee and construction-small pipe, design personnel indicates neither was aware of the regulatory guide requirement or existence of the ANSI, document, It appears the only concern was to design the lines in accordance with the ASIDE code.
This item is unresolved pending NRC review of licensee evaluation of corrective action.
(50-387/80-18-02; 50-388/80-12-02)
6.
Instrument Cable/Terminations
- Work Observations The inspector observed a safety related cable pulling operation in area 12, elevation 783'-0" which consisted of inspection and cleaning of the conduit, preparation of the cable and assembly of cable pull.ing tools.
Cable number FK2D0017J was manually pulled through conduit. F2K458 from junction box 2D62417 to the HVAC panel OC8778.
The inspector reviewed the cable pull card to verify raceway checks, cable routing and material identification.
Licensee gC and QA personnel were present during the cable pulling operation.
No items of noncompliance were identified.
7.
Instrument Cables Terminations - Procedures Review The inspector reviewed a preliminary copy of procedure TP-1.29, Revision 1, entitled."Insulation Resistance Testing of Single Conductor 810 (011)
Cable."
This document prescribes conditions for testing and acceptance criteria for single conductor 810 (011) cable.
The inspector noted that a test crew was applying the procedure to non-safety related cable as a means of training for technicians and an opportunity to debug the procedure.
No items of noncompliance were identifie.
Unresolved Items Unresolved itemsare matters about which more information is required in order to ascertain whether they are acceptable'items or items of noncompliance.
Unresolved item(s) identified during this inspection are discussed in Details, Paragraphs 4 and 5.
9.
Exit Interview The inspector met with licensee representatives (denoted in Details, Paragraph 1} during the inspection at the Corporate Office in Allentown, Pennsylvania on July 2l, 1980 and with licensee and construction representatives at the conclusion of the inspection at, the site in Berwick, Pennsylvania on August 1, 1980.
The inspector summarized the purpose and scope of the inspection and identified the inspection results.
The NRC Senior Resident Inspector was present for the meeting at the site.