IR 05000387/1979040
| ML17138B107 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/09/1980 |
| From: | Gallo R, Mcgaughy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138B106 | List: |
| References | |
| 50-387-79-40, 50-388-79-21, NUDOCS 8002290573 | |
| Download: ML17138B107 (8) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION ANO ENFORCEMENT Region I 50-387/79-40 R
p N
. ~50-388 79-21 50-387 Docket No. 50-388 CPPR-101 License No. CPPR-102 Priority Category Licensee:
Penns ivan'a P wer
'
C m
n 2 North Ninth Street Allentown Penns lvania 18101 Facility Name:
Sus uehanna Steam Electric Station I'nspection at:
Salem Township", Pennsylvania Inspection conducted:
November 5-30, 1979 Inspectors:
. M. Ga lo,. Resident Reactor Inspector date signed date signed da e
igned
'pproved by:
R.
. McHaughy, Chi jects Section, RCEES Branch d te signed Ins ection Summar:
Unit 1 Ins ection on November 5-30 1979 Reoort No. 50-387/79-40 reas Ins ected:
Routine inspection by the Resident Inspector of:
installation an we ing of reactor coolant pressure boundary and other piping; installation of safety-related components; ACR/PGCC rework",, containment load testinq; 50.55(e)
'reports; procedures and work in progress for the Reactor Pressure Yesse1 Recircu-lation System nozzle modification.
The inspector also performed plant tours and reviewed licensee actions on -previously identified items.
The insnection involved 32 inspector-hours, including 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during off shift by the NRC Resident Inspector.
Results:
Ho items of noncompliance were identified.
Unit 2 Ins ection on November 5-30 1979 Reoort No. 50-388 79-21 reas Ins ecte
Routine inspection by the Resident Inspector of:
installation n
we ding of reactor coolant pressure boundary and other piping; installation of safety-related components.
The inspector also performed plant tours and reviewed licensee actions on previously identified items.
The inspection involved 9, inspector-hours by the NRC Resident Inspector.
11'esults,,',.(o item" of noncompliance were identified.
s SOD2290
DETAILS-Persons Contacted Penns lvania Power 8 Li ht Com an Note R.
P.
G.
E.
S.
R.
M.
J.
E.
Beckley, Site QAE Brady, Project Engineer-Construction Burvis, Site QAE Carroll, Site QAE L. Denson, Assistant Project Construction Manager H. Featenby, Project Construction Manager Gorski, Resident Engineer Green, Resident NQA Lazarowitz, Resident Engineer F. Oldenhage, Resident Engineer
1,
1', 2,.4 R. Petr okonis, Project Engineer-Construction D., B. Ritter, Project Engineer-Construction A. R. Sabol, Manager, Nuclear Quality Assurance R. A. Schwarz, Senior Project Engineer-Construction Bechtel Cor oration G.
C'. Bell,. Bechtel QAE J.
G. Berra, Project Superintendent Services M. A. Drucker, Electrical QAE J. Colker, Lead Pipe/Mechanical Engineer G.. Gelinas, QC Lead Engineer Piping/Mechanical J.
Khandar, Mechanical QAE A. Konjui a, Mechanical QAE H:.: Lilligh, Project QAE Minor, Project Field Engineer O'ullivan, Assistant Project Field Engineer
1,
2.
1 3 ~
B. Ott, Lead Melding QCE W.. Ross, Lead Welding Engineer K. Stout, Project Field QCE C., Turnbow, Field Construction Manager General'lectric Com an -Nuclear Ener Business Grou NEBG 1,
1,. 3 E.
J.
A. Gustai'son, Site Manager C. Walker, QA/QC Representative
General Electric Com an -Installation
& Service En ineerin I&SE G. Bragan, Site Manager
J.
Kong, Project Manager Recirculation System Nozzle Modification Peabod Testin Com an M. Whalen, NDE Supervisor
. Notes 1 - Denotes those present at 2 - Denotes those present at 3 - Denotes those present at 4 - Denotes those present at the exit interview, November',
1979.
the exit interview, November 16, 1979.
the exit interview, November 21, 1979.
the exit interview, November 30, 1979.
The inspector also interviewed other PP&L employees, as well as employees of Bechtel, Peabody Testing Company, and General Electric Company.
2.
Plant Tours - Units
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 noncom-pliance 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 preser-vation.
The inspector interviewed craft personnel, supervision and quality inspection personnel as such personnel were available in the work areas.
No items of noncompliance were identified.
3.
Licensee Action on Previous Ins ection Findin s a ~
(Open} Noncompliance (387/78-15-01):
Failure, to qualify welders for the. welding process in use.
The inspector reviewed the licensee's actions relative to this matter.
GE Installation and Service Engineering's (GEI&SE) Weld and NDE Spread Sheet 160-77E-0155, Revision 8, had been revised and submttted to Bechtel for approval.
Dlscrepanci;es identified by Bechtel'aused Revi.sion 8 to be rejected.
Revision 9 tq the Spread Sheet was prepared and resubmitted by GEI&SE.
The jnspectop expressed his concerns regarding the delay in. completing the corrective steps taken in response to this item of noncompliance, as discussed in the licensee's letter to the NRC, PLA-302, dated November 20, 1978.
The matter remains open pending verification of completion of the licensee's committed action b.
'(Closed)
Unresolved Item (387/79-31-03; 388/79-16-01):
Cooper Energy Services Diesel Overspeed Shutdown Butterfly Valve Spring.
The. inspector had inquired if the new valve springs could be differen-tiated from the replaced defective springs.
By letter, dated November 9, 1979, to Bechtel, the Cooper Energy Services Senior guality Control Engineer provided the defective spring and the replacement: spring serial numbers.
The inspector had no further questions on this matter at this time.
c.
.(Closed)
Unresolved Item (387/79-31-06):
Installation of CR-2940 control switches without locking rings.
The inspector had previously observed that Unit 1 control room panels had locking rings installed in accordance with GE FDI WJEG.
The inspector also observed that the NSSSS Manual Isolation Switches for Unit 1 had locking rings installed but those for Unit 2 did not have locking rings.
Upon investigation, the inspector determined that the NSSSS Manual Isolation Switches were in fact Cutler-Hammer 10250T switches.
By memo, serial number SS-79-26, dated October 29, 1979, the GE Principal Engineer stated that this switch did not require a
locking ring but that there was no adverse effect if a locking ring was installed.
The inspector had no further questions on this matter at this time.
d.-
(Open)
Unresolved Item (387/79-31-07):
High Pressure Coolant Injection (HPCI) System Pump Installation.
The licensee's Resident NgA Engineer issued PPSL Deficiency Report (DR) No.
99 on October 19, 1979.
The DR required
"Stop Work" action regarding the HPCI pump alignment and discharge piping installation.
The "Stop Work" release was granted on November 27, 1979, based on the gA review and acceptance of Bechtel FCI-M-178, Revision 0.
This matter remains unresolved pending completion of NCR 4346 and FCI-M-178.
4.
Reactor Coolant Pressure Boundar 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 Appen-dix D, the Bechtel guality Assurance Manual Section III, Site Specifications M204, M207, Drawings M-198 and M-199, and GE Specifications 24A4628.
Weldin
- Unit 2 Welding of:
VNB-B21-3-FW-C3
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 rela-tive 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 (GEI&SE) work; and ASME Section III thru Winter, 1972 Addenda for Bechtel work; and commit-ments in PPEL letters, to the NRC, PLA-291, dated September 25, 1978, and PLA-350, dated May 4, 1979.
Procedures reviewed included:
Bechtel ICI No.
18, Revision 4.
GEI8SE Procedures:
SRSE 1-12, Revision 3; SRSE 1-18, Revision 5; and SRSE 1-19, Revision 0.
The inspector observed work in progress and verified conformance to applicable procedures.
Specific observations included:
Welding of safe-end to thermal sleeve (Weld No. 3) - N2F nozzle.
Welding of safe-end to nozzle (Weld No. 2) - N2A nozzle.
b.
During observation of work in progress on nozzle N2A, the inspector reviewed the calibration record for machine welder serial number 119
'he calibration test report reviewed was part of a Bechtel calibration procedure ICI No. 18, Revision 4.
The inspector inquired'f the Bechtel calibration procedure had been approved for use by GEISSE.
This item is considered unresolved pending the licensee's evaluation and review by the NRC (387/79-40-01).
The inspector also observed that step number 5.10.10 on the calibra-tion test report included a reading of 10.74 VOC where the specified minimum voltage was specified as 10.89 VDC.
The inspector stated that this reading should have been adjusted to be within specification or evaluated prior to field use of the equipment.
This matter is con-sidered unresolved pending the licensee's evaluation and review by the NRC (387/79-40-02).
6.
ACR/PGCC Rework Control Panel Insert 72C
~
~a.
B letter dated November
1979, the licensee reported that connec-tor pin crimping defects on control room panel insert P853-72C were considered reportable in accordance with 10 CFR 50.55(e).
This condition had been previously reported to the NRC in accordance with 10 CFR
by General Electric Company.
Further examination of'the repairs will be conducted during a future NRC inspection.
b.
During this inspection the, inspector noted that flexible conduit had been added to cables between the insert and the stationary bench board.-
The flexible conduit is presently supported at the stationary bench board end by tie wraps.
The inspector inquired if this was to be final installation and if this system.had been seismically quali-fied.
The inspector was informed that the final installation was still under review and this matter would be addressed.
This matter is considered unresolved pending inspection of the licensee's final installation (387/79-40-03; 388/79-21-01).
7.
Coo er Ener Services Diesel En ine Modifications a
~
b.
Cooper Energy Services, supplier of the Susquehanna Emergency Diesel Generators, advised the NRC by letter, dated November 3, 1978, of a deficiency in the design of the crosshead assembly roller pin.
During this inspection, the inspector observed work in progr ess to replace the crosshead assemblies.
By letter to Hechtel, dated November 15, 1979, Coopers Energy Services provided the part number for the redesigned crosshead assembly.
The inspector had no further questions at this time.
In addition, the inspector inquired what testing had been or would be accomplished to verify the engine modification.
The inspector stated that it appeared that the commitment to Regulatory Guide 1.9 and IEEE 387-1972 in FSAR Section 8.1.6 called for testing.
The inspector also noted that FSAR review question 040.65-X10, addressed diesel engine qualification testing.
This matter is considered unresolved pending licensee evaluation and review by the NRC (387/79-40-05; 388/79-21-,
03).
8.
Submer ed Bubb'le Load Test The inspector observed work in progress regarding the proposed submerged structures bubble load tests at Susquehanna.
The objective of these tests
is to measure loads on, and response of, submerged structures in the Susque-hanna pressure suppression pool when subjected to loads from-a simulated safety-relief valve line air-clearing bubble.
The inspector examined installation of bubble chamber, associated pressure gages and sensor instrumentation.
The inspector also reviewed the "Test Plan for Submerged Structures Tests at SSES," Stanford Research Institute Document No. 5881-43, Revision B.
The tests are expected to be conducted in December, 1979.
No items of noncompliance were identified.
9.
Reactor Coolant Pressure Boundar and Safet -Related Pi in
- Unit
The inspector examined work activities relative to turnover to the startup group of the feedwater system.
The system turnover boundaries are defined by Startup System Turnover No. 145A.2.2.
The inspector examined documenta-tion relative to the system turnover and observed the installed feedwater system piping.
The inspector verified that the system turnover was being accomplished in accordance with applicable procedures, the PSAR Appendix D, and FSAR commitments.
The above activities were evaluated against criteria established in the following documents:
FSAR Sections 5.4.9 and 10.4.7 Bechtel gA Manual,Section I.II Bechtel Drawings M-26-5, M-141, OBB-118-1, DBB-119-1, DLA-103-1, and DLA-101-1.
PPSL Administrative Directive 6.1, Revision
Bechtel Field Procedure FP-G-19, Revision
Bechtel QC Project Special Provision Notice G-7.4, Revision
System Turnover Exception Form The inspector noted that FSAR Section 5.4.9.3 did not describe the as-built construction of the feedwater system containment isolation valves.
FSAR Figure 5.1-3a and Bechtel Drawing M-141 show the correct as-built condition of the feedwater system isolation valves.
This matter is considered unre-solved pending the licensee's revision to the FSAR (387/79-40-06).
10.
Deficienc In the S stem For Isolatin Non-Class lE Loads Connected To the 250 VDC E
S stem By letter to the NRC, dated November 14, 1979, the licensee reported a
deficiency in the electrical isolation system in accordance with 10 CFR
50.55(e).
The inspector reviewed PPSL Deficiency Report (DR) 0134 regard-ing this deficiency.
The DR states that the isolation systems for the 250 VDC Class lE system connections to the Non-Class lE loads do not meet the intent of the FSAR Sections 8.3. 2. 1.,1. 2, 8. 1.6.1(m),
and 3.12.3.4.1.
Resolution of'he 50.55(e) report and PPSL DR 0134 will be reviewed during a subsequent inspection.
No items of noncompliance were identified.
ll.
Deficienc Re ardin Violation of Se aration Criteria for 4.16 KV Switc ear By letter to the NRC, dated November 29, 1979',
the licensee reported a
deficiency, involving separation criteria for vendor supplied electrical panels and switchgear,'n accordance with 10 CFR 50.55(e).
The inspector reviewed Bechtel MCAR 1-38 regarding this deficiency.
The MCAR states that separation requirements committed to in FSAR Section 3.-13.1 (Regulatory Guide 1.75) were never incorporated into project specifications to govern vendor wiring.
An analysis of the interal wiring of all electrical panels and switchgear on a case by case basis is in progress.
Resolution of the
.
50.55(e) report and MCAR 1-38 will be reviewed during a subsequent NRC inspection.
No items of noncompliance were identified.
~
~
12.
Unresolved Items Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, items of noncompliance, or deviations.
Unresolved items.disclosed during this inspection are dis-cussed in Paragraphs 5.b, 6.b, 7.a, 7.b, and 9.
13.
Exit Interviews At periodic intervals during the course of this inspection, meetings were held with facility management (dates and.attendees are denoted in Detail 1)
to discuss i'nspection scope and findings.