IR 05000410/1978007
| ML17053A259 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/06/1978 |
| From: | Bateman W, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053A258 | List: |
| References | |
| 50-410-78-07, 50-410-78-7, NUDOCS 7811300387 | |
| Download: ML17053A259 (10) | |
Text
5
N U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Il I N.NOO License No. CPPR-112 Priority Category Licensee:
Nia ara Mohawk Power Cor oration 300 Erie Boulevard, West S racuse, New York 13202 Facility Name:
Nine Mile Point Nuclear Station, Unit 2 Inspection at:
Scriba, New York and Syracuse, New York Inspection con ted:
Septe ber 26-28, 1978 Inspectors:
L. Narrow, Reactor Inspector W.
H. Bateman, Reactor Inspector lo
7P-date signed 0-'
date signed Approved by:
R.
W. McGaughy C ', Construction Projects Section, RC 5 ES Branch date signed g
date sig ed Ins ection Summar
Ins ection on Se tember 26-28 1978 Re ort No. 50-410 78-07 d:
I
,
d
I by NI I
b d I
5 5 tive maintenance program during shutdown of construction; the gC program for "risk release" of equipment; vendor documentation for safety related equipment; and the status of out-standing items.
The inspection involved 46 inspector-hours on site and at the licenseds office by two NRC inspectors.
Results:
No items of noncompliance were identified.
'F8118g e @g7 Region I Form 12 (Rev. April 77)
DETAILS Persons Contacted
- R. J. Aldrich, gA Engineer
+J. J.
Bebko, Project gA Engineer
- W. M. Bryant, Manager, guality Assurance
- R. A. Dowd, Supervisor, guality Assurance
- C. D. Terry, Senior Site gA Representative K. D. Ward, gA Engineer Stone and Webster En ineerin T. Bowden,-Field gC, Structural B.
W. Gatlin, Superintendent Field gC L. Martiniano, Senior Field Engineer K. Schinners, gC Data Control Supervisor The inspector also interviewed other licensee and contractor employees during the inspection.
- denotes those present at the exit interview.
Plant Tour The inspectors made a tour of the site to observe work activites in progress, completed work and the status of construction.
The inspector examined work items for any obvious defects or noncompliances with regulatory requirements and observed gC activities and evidence of quality control of the work.
Specific activities observed by the inspector included fit-up and welding of containment liner, placing reinforcing steel for the Control Building and Auxiliary Building, and preplacement activities for the screen well base mat.
No items of noncompliance were identified.
Equi ment Maintenance The inspector examined a sampling of equipment preventive mainten-ance records for July,and August, 1978, during shutdown of construc-tion. Preventive maintenance had been performed except that rotation of certain pumps could not be performed as scheduled due to unavail-ability of the necess'ary craft personnel.
Unsatisfactory inspection re-ports have been written for this equipment and Nonconformance and Disposition (N 5 D) Report No.
0670 has been issued.
The inspector had no further questions concerning this matte t
4.
Risk Release of E ui ment The inspectorexamined the documents listed below for control of release of nonconforming equipment and material(risk release}to construction.
guality Assurance Program, Rev.
6.
guality Standard gS 15.2, Rev. A, Change Notice No. 4,
"Risk Release."
gC Instruction FN2-S15.3-010,,
dated September 2, 1977,
"Risk Release of Nonconforming/ Unsat.
Equipment and Material."
The inspector reviewed approximately 505 of the "risk releases" which had been issued.
The releases had been documented and approved in accordance with the procedures identified above.
No items of noncompliance were identified.
5.
Vendor Documentations The inspector examined the documentation package for the below listed components to verify that Nuclear Steam System Supplier (NSSS)
purchase material documentation is in compliance with NSSS purchase specification requirements and Paragraphs D.3.8 and D.4.4.5 of Appendix D of the PSAR.
(1)
2RCS-MOV-10A 8 B-Recirculation Valves (2)
2RHS-P-1A-Residual Heat Removal Pump Site personnel whose purpose it is to examine documentation for completeness were interviewed.
The site quality assurance procedures were reviewed to ensure that a program was available to receive review, organize, store, and retrieve documentation.
No items of noncompliance were identified.
6.
S acin of Reinforcin Steel During the plant tour (Paragraph 2, above)
the inspector noted that spacing of reinforcing steel for the screen well base mat, Pour No. 5-310-025P,,did not, at some locations, meet the requirements of ACI 318 which is referenced in the PSAR as one of the structural codes.
The required preplacement inspection of this part had
~W
not been performed by gC.
This item is unresolved pending rework of the. rebar installation to provide the proper spacing and its inspection by field QC.
(78-07-01)
Licensee Action on Previous Ins ection Findin s (Closed)
Unresolved Item (78-06-01):
409 for revision of the requirements for tests of reinforcing steel for unacceptable inclusions has been approved.
Review of Nonroutine Events Re orted b
the Licensee By letter dated October 5, 1977, the licensee had reported the existence of the potential for rock stress at the site and that this might affect the wall of an electrical tunnel.
A study and analysis of this problem has been completed and a summary of the results has been submitted,to the Office of Nuclear'Reactor Regulation.
The licensee will also address this problem in the Final Safety Analysis Report.
This item is resolved.
Licensee Action on IE Bulletins and Circulars The inspector examined records and interviewed licensee representatives to verify that corrective action had been taken with respect to IE Bulletins and Circulars.
For each of the Bulletins shown below the inspector verified that the identified equipment had been added to the Excluded Equipment list of the appropriate specification.
In addition licensee's Audit No.
15 of GE has confirmed that GE is taking the necessary actions for control of Bul.letin and Circular information, and licensees Audit No.
27 had resulted in S8W Generic Change Notice (GCN) No.
0024 for incorporation of current Excluded Equipment Lists in equipment specifications for safety related equipment.'ulletin 74-12 Closed.
Westinghouse Type SG RelaysBulletin 78-05 Closed.
GE Auxiliary Contact Mechanisms (CR 105X-CB)
Bulletin 78-06 Closed..
Cutler Hammer Type M Relays The inspector also verified that S8l<,Engineering had reviewed the circulars listed below and established design requirements in accordance with the information and recommendations contained there in ~
Circular 77-03 Closed.
Fire in ITE Motor Control Center Circular 77-15 Closed.
Degradation of Fuel Oil Flow to Emergency Diesel Generator.
Circular 78-04 Closed.,
Installation Error That Could Prevent Closing of Fire Doors.
10.
Unresolved Items Unresolved items are matters about which more information is required in order to. ascertain whether they are acceptable items, or items of noncompliance.
An unresolved item disclosed during the inspection is discussed in Paragraph 6.
ll.
Exit Interview At the conclusion of the inspection on September 28, 1978, a
meeting was held with representatives of the licensee.
The inspectors summarized the results of the inspection as described in this repor '1