IR 05000387/1979041
| ML17138B275 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/30/1980 |
| From: | Gallo R, Mcgaughy R, Rhoads G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B271 | List: |
| References | |
| 50-387-79-41, 50-388-79-22, NUDOCS 8005020151 | |
| Download: ML17138B275 (16) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EHFORCEMEHT Region I 50-387/79-41 R
p R
Docket No.
License No.
I Licensee:
50-387 50- 88 CPPR-101 CPPR-102 Priority Penns lvania Power 8 Light Com an Category 2 North Ninth Street Allentown,'enns lvania 18101 Facility Name:
Susquehanna Steam Electric Station Inspection at:
Salem Township, Pennsylvania Resident Inspector Inspection conducted:
December 3,
1979 - January 4,
1980 Inspector'
M. Gallo, S
g dat ign d
G.
G. Rhoads, R
e t Inspector date igned Approved by:
c aug, se, rogects ection RCSES Branc date signed dat igne Ins ection Summar
Unit 1 ins ection on December'3.
1979 - Januar 4,
1980 Re ort No. 50-387 79-41
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l litt and welding of'eactor coolant pressure boundary.,and other piping; installation of safety-related, components; submerged bubble load and impulse tests; procedures and work in progress for the Reactor Pressure Vessel Recirculation System nozzle modification; installation of safety-related pipe support and restraint systems; IE Bulletin and Circular Followup.
The inspector also performed plant tours and reviewed li'censee actions on previously identified items.
The inspection involved 86 inspector-hours, including 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during off shift, by the HRC Resident Inspectors.
Results:
Of the seven areas inspected, no items of noncompliance were identified
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sn ssx areas; one apparent item of noncompliance was identified.
(Infraction-failure to use controlled drawings to verify pipe support installation - Paragraph 9.b).
Region I Form 12 (Rev. April 77)
Seososo i
Unit 2 Ins ection on December 3.
1979 - Januar 4,
1980 Re ort No. SO-388/79-22)
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I t and welding of reactor coolant pressure boundary and other piping; IE Bulletin and Circular Followup.
The inspector also performed plant tours and reviewed licensee actions on previously identified items.
The inspection involved 30 inspector-hours, including 3'ours during off shift, by the NRC Resident Inspector.
Results:
No items of noncompliance were identifie DETAILS Persons Contacted.
Penns lvania Power and Li ht Com an Note R.
G.
S.
E.
T.
S.
J.
R.
E.
M.
J.
E.
To A.
R.
Beckley, Site QAE Burvis, Site QAE H. Cantone, Superintendent of Plant Carroll, Site QAE Clymer, Site QAE L. Denson, Project Construction Manager D. Everett,,
ISG Quality Engineer H. Featenby, Assistant Project Director J. Gorski, Plant Quality Supervisor Gorksi, Resident Engineer Green, Resident NQA Lazarowitz, Resident Engineer F. Oldenhage, Resident Engineer R. Sabol, Manager, Nuclear Quality Assurance A. Schwarz, Senior Project Engineer - Construction
1,
1,
1, 2, 3,
3 2, 3,
Bechtel Cor oration G.
M.
C. Bell, Bechtel QAE A. Drucker, Electrical QAE 1,
3.
J. Colker, Lead Pipe/Mechanical Engineer E.
W. Figard, Assistant ISG Supervisor G. Gelinas, QC Lead Engineer Piping/Mechanical J.
Khandar, Mechanical QAE A. Konjura, Mechanical QAE H. Lilligh, Project QAE T. Minor, Project Field Engineer W. Mour er, Superintendent J. O'ullivan, Assistant Project Field Engineer B. Ott, Lead Welding QCE W. Ross, Lead Welding Engineer K. Stout, Project Field QCE C. Turnbow-, Field Construction Manager Engineer
1,
1,2,3 1,
2.
1, 2, 3,
General Electric Com an -Nuclear Ener Business Grou NEBG E. A. Gustafson, Site Manager General Electric Com an -Installation and Service En ineerin ISSE G. Bragan, Site Manager Peabod Testin Com an M.'halen, NDE Supervisor Notes 1 - Denotes those present at the exit interview December 14, 1979 2 - Denotes those present at the exit interview December 20, 1979 3 - Denotes those present at the exit interview December 28, 1979 4 - Denotes those present at the exit interview January 4,
1980 The inspector also interviewed other PP8L employees, as well as employees of Bechtel, Peabody Testing Company and General Electric Company.
Plant Tours - Units 1 and
The inspector observed work activities in progress, completed work and plant status in several areas of the plant during general inspection of the plant.
The inspector examined work for any obvious defects or noncompliance with regulatory requirements or license conditions.
Particular note was taken of presence of quality control inspectors and quality control evidence such as inspection records, material identification, nonconforming material identification, housekeeping and equipment preservation.
The inspector inter viewed craft personnel, supervision and quality inspection personnel as such personnel were available in the work areas.
E No items of noncompl iance were identifie.
Licensee Action on Previous Ins ection Findin s a ~
b.
c ~
(Closed)
Unresolved Item (387/78-12-03):
Pipe Suppor t Interference The inspector observed the condition of pipe supports GBB-101-H5 and GBB-101-H10.
The inspector noted that previously observed interferences had been removed or supports modified to provide clearance.
The inspector also reviewed Bechtel Specification N-213 Revision 7, dated June 22, 1979, Section 5.1 page 2, requires the responsible Field Piping Engineer to check to assure sufficient clearance between pipe supports and
.adjacent structures to accomodate anticipated thermal expansion.
The inspector had no further questions on this matter at this time.
(Closed)
Unresolved Item (388/79-11-01):
Spent Fuel Pool Pi ping The inspector had noted the appearance of corrosion adjacent to several circumferential welds.
The licensee's construction manager investigated this condition by buffing the, affected areas on pipe spools HCC-201-3, HCC-203-1 and HCC-203-2.
After buffing the welds were wet down and observed for a 24-hour period during which no corrosion reappeared.
These actions and Bechtel gA verification were documented on Bechtel guality Action Request F-525.
The inspector examined selected portions of installed spent fuel pool piping and noted no recurrence of the type of corrosion originally observed.
The inspector had no further questions on this matter at this time.
(Closed)
Item of Noncompliance (387/79-15-01):
Failure to inspect gas purging for tack welds.
The licensee committed to revise the Bechtel guality Assurance Nanual (BgAN), to avoid further items of noncompliance regarding the inspection of gas purging.
The inspector reviewed Amendment 19, dated August 1979, to the B(AN Appendix 3, Paragraph 7.4, Item (13) of Welding Standard Wp-The revised welding standard requires that tack welds be inspected by the gC inspector at the time of fit-up inspection, and if oxidized on the interior surface, the tack welds must be removed.
Site gC personnel were instructed regarding the BREAM amendment on July 2, 1979.
The inspector interviewed selected welding gC inspectors to verify that the BREAM requirements were understood.
The inspector had no further questions on this matter at this time.
d.
(Closed)
Unresolved Item (387/79-28-01):
Post Weld Heat Treatment Procedure Revision The inspector reviewed post weld heat treatment procedure PHT-501 Revision 7 regarding the number and location of thermocouples.
PHT 501 Revision 7, includes Figures PHT-501-2A, 2B, 2C and 2D which provide detailed information regarding the number and location of recording thermocouples.
The inspector reviewed post weld heat treatment records for EBB-102-1 FWll and EBB-102-1 Vendor Weld "A".
The inspector verified that the revised thermocouple requirements of PHT 501 had been observed.
The inspector had no further questions on this matter at this time.
4.
Reactor Coolant Pressure Boundar and Other Pi in Weldin
)
The following activities were examined to determine if they were being performed in accordance with the ASME Section III and IX Codes, PSAR Appendix D, the Bechtel guality Assurance Manual Section III, Site Specifications M 204, M 207, and drawings M-198 and M-199.
Weldin
- Units 1 and
Welding of:
DCA-210-1 FW9 EBB-103-1 FW8 GBC-201-12 FW13
The inspector verified selected detailed drawings, welding procedures, base and filler materials as specified, welder qualification, quality control documentation, weld appearance, welding variables and nondestructive testing activities as appropriate.
No. items of noncompliance were identified.
5.
Recirculation S stem Nozzle Modification - Unit
a ~
The inspector reviewed procedures and observed work in progress relative to the Recirculation System nozzle modification.
The procedures and work were examined to verify conformance with ASME Section III thru Summer 1976 Addenda and Section XI 1974 edition for General Electric Installation and Service Engineering (GE IPSE) work; and ASME Section III thru Winter 1972 Addenda for Bechtel work; and commitments in PP&L letters, to the NRC, PLA-291 dated September 25, 1978 and PLA-350 dated May 4, 1979.
Procedures reviewed and utilized for inspection included:
GE IPSE procedures SRSE 1-4, Revision
SRSE 1-12 Revision 3.
The inspector observed welding work in progress and verified conformance to applicable procedures Specific observations included:
Welding of safe-end to thermal sleeve (Weld No. 3)
N2A nozzle Welding of safe-end to nozzle (Weld No. 2)
N2G nozzle Calibration records and stickers for Dimetrics Welding Machines Serial Numbers 119 and 121
b.
During observation of the aforementioned welding the inspector noted that the calibration sticker for. welding. machine serial number 121 indicated that calibration.was due on October 20, 1979.
The. inspector.also noted that the calibration sticker for welding machine serial'number 119 indicated that ca'libration was due.on March 18, 1979.
GE IPSE provided calibration records which showed that calibration for machine serial
.
number 121 was completed September 26, 1979 and was due for next calibration by March 26,.1980.
The calibration records
,also showed that machine serial number 119 was due for calibration on. March 18, 1980.
Both calibration stickers were corrected.
No items of noncompliance were identified, however, unresolved items 387/79-40-01 and 387/79-40-02 remain open.
6.
Inde endent Confirmator.
Anal sis of Pi in Desi n
7.
The inspector accompanied representatives of the NRC and Pacific Northwest Laboratories on an inspection of Main Steam, Safety Relief Valve and Feedwater piping.
The purpose of this inspection was to obtain information regarding selected systems to be reviewed for a more detailed analysis of the piping system design.
Pacific Northwest Laboratories will perform an independent confirmatory analvsis of the design calculations of a piping run for the NRC.
Submer ed Bubble Load and Im ulse Test The inspector observed work in progress regarding the submerged structures bubble -load test and impulse test at Susquehanna.
The objective of the bubble test was to measure loads on, and response of, submerged structures in the SSES pressure suppression pool when subjected to loads from a simulated safety-relief valve line air-cleaning bubble.
The objective of the impulse test was to measure pool response to a simulated chug load, in the form. of an impulse disturbance in the pool at the end of a vent.
The inspector examined installation of both the bubble chambers,and the impulse chamber, the associated pressure gauges, sensor instrumentation and tools used for proper calibration.
/
The inspector observed the performance of the impulse test, and nitrogen, loading of a balloon as part of bubble test.
The following procedures were reviewed;
Test Plan for Submer ed Structures Tests at SSES Stanford Research.Institute. Document, No. 5881-43, Revision B
A lan for SSES Submer ed Structures Test
'tanford. Research, Institute Document No. 5881-42 Revision 0.
Test Procedures for.
Im ulse Tests at. SSES Stanford Research Institute. Document No. -5881-253 Revision 0.
No items of noncompliance were identified.
8.
Hi h Pressure Coolant In'ection HPCI S stem.
Pum
'Installation Unit
a.
The inspector examined work activities relative to the alignment of HPCI'ump components'and installation of HPCI pump discharge plpi'ng.
PP&L Deficiency Report Serial No.
99 was issued October 19, 1979 to stop work on all activities associated with the alignment of HPCI pump 1P-204 until issuance of specific written instructions regarding those activities.
Bechtel Field Construction Instruction FCI-M-178 Revision
was approved November,27, 1978 and the stop work action was released.
Unresolved, item 387/79-31-07 regarding the disposition of Bechtel Nonconformance Report (NCR) No.
4346 remains unresolved pending completion of work required. by'CR 4346 ahd FCI-M-178.
b.
The inspector observed the post weld heat. treatment of two welds.in the HPCI',. pump-discharge piping.
The post weld heat treatment (PWHT) was specified bv FCI-M-178 Revision 1.
The inspector observed post weld heat treatment and reviewed appropriate records regarding weld joint'numbers EBB-102-1 FWll. and EBB-102-1 Vendor. Weld A, The PWHT was completed in.
accordance with'Bechtel procedure. PHT-501 Revision 7.
No items of noncompliance were identifie.
Safet Related Pi e Su ort and. Restraint Systems a
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The inspector examined. the licensee's'rocedures for final OC inspection and..turnover to the Integrated Startup Group of pipe supports.
The inspector examined these activities relative to commitments. in the PSAR Appendix D, Bechtel Specification'213 Revision.7, guality Control Instruction P2.10B Revision 8, and Field Procedure FP-G-. 19 Revision,3.
The. inspector reviewed final inspection records for supports DCB-102-Hl, H2, and H3.
Discre-pancies identified. by site gC were documented on Nonconformance Report No. 5019.
The inspector determined that an IRF, Installa-tion Review Form, was beirlg used by Field Engineering to notify
'ite gC personnel that specific pipe supports were available for final inspection.
The inspector, noted that, Specification M213 Revision 6 had contained instructions for conducting final review and inspection activities.
This information, was deleted by Revision 7 to the specification, gCI P-2.10B Revision 8, however, still refers to the. instructions found in Revision 6 to Specifica-tion M213.
The inspector was informed that gCI P2.10B was in the process of. revision.
The inspector stated that the instructions for final inspection activities of pipe supports, conducted by Field Engineering and guality Control, were vague and it was difficult to. determine 'how the inspections'ere being controlled.
. -This matter.'is considered unresolved pending 'evaluation by the licensee and-review by the NRC (387/79-41-01).
The inspector. reviewed IRF's for the"turnover of System 149D, a portion of the Residual Heat Removal System.
The inspector
- inquired how it was verified that all pipe supports within given turnover boundaries had been installed and inspected.
Field Engineering personnel'tated, that the drawings used were individual hanger detail drawings, the marked-up Process and -Instrument-Diagram showing the turnover. boundaries and the stress isometrics.
Installation Review Forms are then prepared and sent to gC for final inspection and turnover review.
The inspector determined"that stress isometrics used at the site were not controlled drawings.
The Bechtel Engineering Procedures Manual (EPM) in Section 4.1 and Appendix.B specifically prohibit the.use of stress isometrics for use in fabrication, installation or verification of pipe supports.
Appendix B states that area drawings and pipe support detail drawings control construction and verfication requirement Furthermore, FP-G-19 Revision 3 Section 7.3.1 instructs Field Engineering to conduct a,walkdown and visual inspection of pipe supports in a system prior to turnover utilizing stress isometrics.
The inspector.
found that certain systems 'had.been processed through turnover and accepted by.PP8L using the stress isometrics
. to control'the number of-pipe.supports installed,and inspected.
The following system. turnovers included safety related pipe suppor ts:
Station Service Water 011A.0.1/lllA.0.1 Condensate Transfer and Storage 037B.l/1378.1 Feedwater 145A Final inspections were in process for the following systems which include some safety related-pipe supports:
Standby Diesel Generator Fuel Transfer and Storage 023B.l Residual Heat Removal System Head Spray Piping 149D
't The inspector was informed that although.the above systems had been processed for turnover no pipe supports had actually been accepted by guality Control and turned over.
The inspector stated that the failure to use prescribed drawings to verify pipe support installations was contrary to the require-ments.of 10 CFR 50, Appendix B Criterion V.
(387/79-41-02)
The inspector observed centain PSA Mechanical Snubbers in Unit
Containment which had their protective covers removed.
The inspector observed the following snubbers to be unprotected DCA-110-H17, H29, H30, H33,,H34, GBC-101-H220, H23 Section 4.9 requires that, after installation, the snubber assembly be protected from physical damage due to normal construction activities by providing protective covers.
The inspector was informed that a Nonconformance Report No. 4989 had been issued on December 12, 1979 addressing several snubbers found unprotected.
This item is considered unresolved pending review of corrective action by the licensee.
(387/79-40-03)
10.
IE Bulletin and Circular Followu
- Units 1 and
a.
Discussion IE Bulletin and Circulars issued to PP&L were reviewed to verify the following:
(1)
bulletins and circulars received by PP&L corporate management were forwarded to appropriate individuals within the organization, including station management, for information, review and/or corrective actions as required (2}
PP&L bulletin responses were submitted to the NRC within the, specified time period (3)
licensee reviews and evaluations of bulletins and circulars are complete and accurate, as supported by other facility records and by inspector observations of installed plant equipment
.(4)
corrective actions specified in licensee bulletin responses or internal circular evaluation memoranda have been completed and/or responsibilities have been assigned to specific individuals for completion b.
~Findin s
(1}
The bulletin and circular listed below, along with applicable references, have been satisfactorily dispositioned by the licensee and the inspector had no further comments on the (a)
IEC-78-14, HPCI Turbine Reversin Chamber Hold Down Boltin; Ref.
PLB-8852 dated August 14, 1978, EAG-1002 dated January 9; 1979, FOI-31/68754 dated June 1, 1978.
IEB-79-03 - Lon itudinal Weld Defects in ASME SA-3 2 T e 304 Stain ess Steel Pi e s ools; Ref.
PLA-366 dated June 12, 1979, NCR no.
3802 dated May 3, 1979.
(2)
The following bulletin and circular were reviewed during this inspection with the following comments; (.a)
IEC-78-15 - Tiltin Disk Check Valves Fail to close with ravst in Vertical Position; Ref: PLI-3462 ated Ju y 31, 97, PLB-9798 dated May 10, 1979, PLI-5056 dated May 22, 1979, BLP-11364 dated August 27, 1979 and QAR-8856 -F-560 dated December 12, 1979.
The inspector noted that the circular was received and distributed to appropriate personnel.
Action taken by licensee did not properly control followup actions.
Specifically, permanent tags were to be hung on each vertically mounted tilting disk check valve to notify maintenance personnel to exercise each of subject valves following main-tenance, and to observe disc closes completely by force of gravity alone.
The tags were not permanent in nature, and wording on tags led to confusion over what maintenance personnel were to do.
The same warning statement was to be added to all applicable valve vendor drawings.
This was not done on drawing 8856-P10-A-67-6.
As a result of this inspection QAR-8856-F-560 was written by Bechtel Quality Assurance to remedy the above stated problems.
This item will be further reviewed by NRC upon completion of above QA (b)
Seismic Anal ses for As-Built Safet Related Pi in S stems - IE Bulletin 79-14 By letter to the NRC dated November 2, 1979 the licensee responded to Bulletin 79-14.
The inspector reviewed the licensee's response and informed the licensee that it did not appear to adequately address the information requested by Item 2 of the Bulletin.
Specifically the Bulletin response did not address inspection of systems to verify conformance to the seismic analysis input information.
The inspector was informed that Bechtel was preparing a site procedure to inspect the as-built condition of piping systems.
The inspector reviewed appropriate Bechtel'ocumentation relative to Bulletin 79-14.
The inspector stated that the site procedure being developed to implement the "as-built" inspections would be reviewed for conformance to the require-
.
ments of Bulletin 79-14.
Documents reviewed by the
. inspector included:
Bechtel letter to PP8L BLP-11487 dated October 3, 1979 Bechtel Interoffice Memoranda EMC 4293 dated July
'13, 1979 and EMC 4442 dated October 23, 1979.
No items of noncompliance were identified.
ll.
Deficienc re ardin insulation and device dama e to wirin in A vanced Contro Room ACR Inserts 72C and 73C By -letter to the NRC dated December 17, 1979, the licensee reported a deficiency involving insulation damage to wir ing and device damage in Control Room inserts 72C and 73C in accordance with 10 CFR. 50.55(e}.
The inspector reviewed Bechtel MCAR 1-33 regarding this deficiency.
The MCAR states that the deficiency described if uncorrected could permit shorting and failure of redundant Standby AC Diesel Generator 4.16 kv feeder breakers which could prevent the circuits from performing the designed safety function.
Since occurrence of damaged wiring is random and could occur in any and all. Diesel Generator feeder breaker circuits, the possibility of a failure exists.
The simultaneous degradation and loss of the Standby AC Diesel Generator power supplies could result in a safety hazard to the operation of the plan The inserts were removed from the panel and sent to GE - San Jose for repair/rework.
GE - San Jose completed this work, and the inserts have subsequently been re-installed in panels.
Resolution of the 50.55(e) report will be reviewed during a subsequent inspection.
No items of noncompliance were identified.
12.
Unresol ved Items Unresolved items are matters about which more information is required to ascertain whether they. are acceptable items, items of noncompliance, or deviation.
Unresolved items disclosed during the inspection are discussed in paragraphs 9.a and 9.c.
13.
Exit Interviews At periodic intervals during the course of this inspection, meetings were held with facility management (dates and attendees are denoted in Details 1) to discuss inspection scope and finding ~
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