IR 05000410/1986048
| ML17055C412 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/11/1986 |
| From: | Eapen P, Oliveira W, Winters R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17055C411 | List: |
| References | |
| 50-410-86-48, NUDOCS 8609230068 | |
| Download: ML17055C412 (22) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-410/86-48 Docket No.
50-410 License No.
CPPR-112 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 Inspection Dates:
Au ust
15 1986 Inspectors:
Wi liam Oliveira, Reactor Engineer R.
W. Winters, Reactor Engineer Wrr Ed d
e s ~44 date Approved by:
Dr
'P.
K. Eapen, Chief, Quality Assurance Section, Operations Branch, DRS, RI err gg d te Ins ection Summar
- Rountine unannounced inspection on August 11-15, 1986
~ Report No. 50-410/86-48)
<<fi, II 1i
Operations in the area of Tests and Experiments and licensee actions on previously identified NRC concerns.
Results:
No violations were identified Sb092gOOb8 SOOOA10 PDR ADOCH 0 PDR
DETAILS 1.0 Persons Contacted Nia ra Mohawk Power Cor oration NMPC
"R. Abbott, Station Superintendent
"D. Baker, Lead Modification Engineer J.
Bunyan, Lead Project Engineer Electrical
~K'ahlberg, Site Maintenance Superintendent W. Drews, Technical Superintendent
~I. Fenton, Quality Assurance (QA) Audit Group Lead R. Gayne, Superintendent of Operations W. Hanley, Manager, Contracts/Purchasing and Materials
"W. Hansen, Manager, Nuclear QA Operations
"A. Kovac, QA Audit Supervisor H. Masters III, QA Engineer (Unit 1)
B. Morrision, Project Quality Engineer
- I. Weakley, Special Projects W. Yeager, Manager of Engineering Stone and Webster En ineerin Cor oration W. Adams, Test Engineer J. Giler, Modification Engineer B. Gillard, Test Engineer B. Rao, Test Engineer T. Rippel, Test Engineer United States Nuclear Re ulator Commission
"C.
Mar schall, Resident Inspector (Unit 1)
~Indicates those who attended the exit meeting on August 15, 1986 The inspectors also interviewed other site and contractor personnel during the inspection.
2.0 Onsite Or anization and Staffin
~~
R~ "i Organizational charts, plans and procedures were reviewed and discussed with licensee personnel to verify the following:
The onsite organizational structure was as described in the proposed facility Technical Specifications (TS) and Final Safety Analysis Report (FSAR).
Personnel qualification levels were in conformance with applicable codes and standards described in the proposed TS and FSAR ~
Lines of authority and responsibility were consistent with the proposed TS and FSAR.
Changes or differences were or are to be reported to the NRC as required by the proposed TS.
2.2 Staffin and Or anization
'or purposes of this report the term "Site" refers to the Nine Mile Point complex encompasing both Units 1 and 2.
Functions dedicated to an individual unit on the site are designated by unit number.
The General Superintendent Nuclear Generation is responsible for the operation and technical support of the Nine Mile Point Nuclear Site.
Reporting to him are the Site Technical Support Superintendent, Site Superintendent Training Nuclear, Site Superintendent Chemistry and Radiological Management, Site Maintenance Superintendent, and the Station Superintendents for Units 1 and 2.
This organization is responsible for the day to day Site operations.
Upon request En-gineering support is provided by the corporate offices.
guality Assurance reports to the Vice President guality Assurance located at the corporate offices.
An assessment of the adequacy of the types and numbers of employees in the Site support organizations'nd the Unit 2 organizations was peyformed to assure the capabilities and operational readiness of those groups.
Discussions were held with various licensee managers and line personnel.
2.3 Personnel ualifications Resumes were reviewed and interviews were held with selected personnel in the support, operations, and guality Assurance organizations to verify qualifications and experience conformed to the Technical Specifications and Final Safety Analysis Report.
2.4 Conclusions Based on the review of this area, it was determined that the onsite operations and support organizations were adequately staffed with respect to their assigned responsibilities't was noted that the present operations staff reporting to the Unit 2 Station Superintendent was significantly larger than the comparable staff in Unit 1.
This was to meet the increased work load during the preoperational test and startup of Unit 2.
The staffs of both units will be more evenly balanced when Unit 2 goes into commercial operatio P
'
At the time of this inspection the position of Supervisor Fire Protection was open.
A qualified individual has been identified
" for this position.
The licensee expects to fill this position by commercial operation.
In the interim one of the Assistant Supervisors Fire Protection is acting as Supervisor.
A recent change to upgrade the Training Department organization was not reflected in the FSAR.
The licensee stated that the current Training Department organization will be incorporated into the FSAR during the next update.
No violations were identified.
3.0 ualit Assurance Pro ram Tests and Ex eriments Procedures listed in Attachment A were reviewed, and interviews were held with licensee personnel to verify the following:
The licensee's program includes controls to assure tests and experiments involving safety related components, systems or structures or 'modes of operation different from those described in the FSAR have been adequately reviewed.
The program includes controls to assure all tests and experiments are conducted using approved procedures.
The program includes controls to assure test and experiment procedures are reviewed by responsible individuals.
The program includes controls to assure unreviewed safety questions and changes to Technical Specifications are reported in accordance with 10CFR50.59.
3.2 Pro ram Im lementation The inspector selected the following five modification packages to verify the program was satisfactorily implemented:
PN2Y86MX069,
"Add Drip Leg Drain to 2ICS-004-61-2" PN2Y86MX073, "Modify Sti llwells and Instrument Location for 2SWP~LS073A 8( B" PN2Y86MX079, "Revise Control Logic" M10028(PR5261),
"Add Cables to Reactor Protection System" 83-87 (Unit 1),
"Emergency Condenser Piping Replacement"
e
The inspector toured the'reas affected by the modifications, and witnessed some of the tests conducted for modification M10028(PR5261).
He observed that the modification activities were conducted by both licensee and Stone and Webster Engineering Corporation (SWEC) contractor personnel.
The activities were conducted in accordance with Site Operations Review Committee (SORC) approved procedures by personnel knowledgeable in the requirements of the procedures and proposed Technical Specifica-tions.
For the modifications selected, the licensee's QC Organization was notified of the activities but was not required to witness any testing.
A review of the procurement and receiving inspec-tion records for material used for modifications PN2Y86MN069 and 079 showed the material had been purchased and received by SWEC and issued in accordance with applicable procedures.
3.3 Conclusions Based on the review of the procedures and observations made duing the inspection it was determined that the Test and Experiment
.
Program was in conformance with the requirements of 10CFR50.59, the proposed Technical Specifications, and the FSAR.
No violations were identified.
4.0 ualit Assurance Audits In NRC Inspection No. 50-410/86-11, the inspector reviewed Corporate Audit Report No. SY-RG-IN-85002 for the System Standards Laboratory in Syracuse.
The report was issued in August 1985 and identified several deficiencies.
One deficiency identified in Corrective Action Request (CAR) 853003 dealt with the use of instruments supplied by two vendors (John Fluke Manufac-turing Company, and General Electric Company - Instruments, Schenectady, NY) who were not on the Qualified Contractors List (QCL), for safety-related application.
(The licensee evaluates each vendor's ability to perform his intended function using an indepth audit.
If qualified, the vendor will be placed on QCL.)
The response to the above corrective action from the licensee's Meters and Laboratory stated that there were at least fifteen additional suppliers who were not on the QCL and requested that QA complete the required audits so that these suppliers may be added to the QCL.
The Meters and Labora-tory further stated that their own scrutiny indicated that there was no reason to disqualify the statements of accuracy or traceability of the instruments provided by the two suppliers identified in the CARs.
The audit personnel informed the inspector that suppliers identified in the above CAR were subsequently incorporated in the QCL.
The inspector reviewed the current QCL and verified the John Fluke Manufacturing Company and General Electric Company Instruments, Schenectady, NY, were on the QCL.
The licensee also stated that the qualification status of the other
A a
suppliers stated in the response section of CAR 853003 was not available at the site and would be made available to the inspector during a future NRC inspection.
During this inspection, the status of qualification of fifteen suppliers mentioned in the response to CAR 853003 was reviewed.
As documented in the letters to file dated May 28, 1986 and August 14, 1986 from the lead auditor for Audit No. SY-RG-IN-85002, the licensee has incorporated all of the above fifteen suppliers in the QCL.
The NRC inspector verified this by reviewing the latest revision of the QCL.
In addition, the inspector reviewed the reports of five other audits (NC-RG-CO-85032 and 85038, NC-RG-IN-85039, NM-RG-IN-86016 and 86017)
and found these reports to be complete with audit announcement letter, attribute list and the final audit reports.
The CARs were initiated, reviewed, approved, responded to and dispositioned effectively in accord-ance with the licensee's procedure QAP 16.03.
The audit personnel were knowledgeable in the requirements of QAP 16.03.
No violations or deviations were identified.
5.0 Followu of Previousl Identified Items Closed Unresolved Item 86-36-01:
The licensee did not identify those instruments needed to be calibrated and did not develop a preventive maintenance
'program for such instruments.
In response to this item the licensee has identified all the instruments needing calibration and developed a calibration schedule for such instruments in accordance with the licensee's administratative procedure.
The inspector reviewed this schedule and noted that no equipment requiring calibration and/or maintenance was overdue.
This schedule has been presented to the Scheduling Department for inclusion in the computer tracking system to assure timely notification of calibrations/ maintenance due dates.
This item is closed.
Closed Construction Deficienc 86-00-13:
The magnitude and location of water hammers in the service water system are different from those discussed in the facility's Final Safety Analysis Report.
On July 2, 1986, the licensee reported to the NRC that an analysis indicated that the location and magnitude of a water hammer induced by the trip and restart of two service water pumps are more limiting than those induced by the trip and restart of all four service water pumps.
To resolve this concern the licensee's architect engineer recommended the following corrective actions:
- 1.
The control logic for valves 2SWP*MOYSOA and 2SWP*MOY508, which are located in the cross connection piping between Division I and Division II service water subsystems, be revised such that the valves remain open during a two pump trip in either Service Water System Division.
2.
The service water pump restart, for the loss of offsite power event, be revised to 32 seconds following start of the emergency diesel generator.
The inspector verified the above corrective actions have been implemented as recommended.
This item is closed.
Closed Unresolved Item 86-22-01:
The licensee has not developed the required procedure to control the receipt, processing and distribution of controlled documents, and to assure that voided, superceded and cancelled documents are removed promptly.
The inspector verified that the licensee has implemented procedure AP 10. 1 for this purpose.
The effectiveness of the implementation of this procedure will be assessed during the operational phase of Unit 2.
This item is closed.
Closed Unresolved Item 85-13-05:
Timeliness of. Quality Control (QC)
inspection of Catagory I stairtowers.
The inspector determined that the stair was erected by the Cives Steel Company under contract to Stone and Webster Engineering Company.
The stair was originally purchased as Catagory II thus resulting in an unsatisfactory condition.
The inspector verified the delay in final inspection was caused by the actions necessary to bring the stair into compliance with Catagory I requirements and subsequent releasing of the area by Stone and Webster.
The inspector reviewed Quality Control Inspection Report S6A61265 and verified that this stairtower was inspected by QC on June 30, 1986.
This item is closed.
Closed Unresolved Item 86-13-02:
The first anchor or triaxial supports beyond the seismic category I boundary were not on the licensee's safety r elated component list (Q list).
Regulatory Guide 1.29 recommends that Seismic Catagory I and non-Catagory I system interfaces be extended to the first anchor or triaxial support system beyond the Code class boundry and that supports in these sections be designed to the requirements of the seismic system.
The licensee was not committed to this Regulatory Guide during construction.
Therefore, the supports, although designed as seismic supports, were classified as QA Catagory II (non-seismic, non-safety related)
items on drawings.
The licensee,
.4
A
however, has committed in the FSAR to Regulatory Guide 1.29 to treat these supports in the operational gA Plan as Catagory I.
The licensee committed to include these supports in the plant "g" list (an automated computer listing of Catagory I safety related items) for plant operations.
The inspector reviewed the list of supports meeting the above criteria, generated by the licensee and selectively verified these supports were properly identified as Catagory I on the Master Equipment List.
This item is closed.
Closed Ins ector Followu Item 83-00-08 Debris in tube steel members:
The inspector selectively examined installed tube steel members in areas turned over to operations and observed the members to be free of flammable and non-flammable debris.
This item is closed.
.Closed Construction Oeficienc Re ort 86-00-07:
On May 8, 1986 the licensee reported a problem in accordance with 10CFR50.55(e).
The problem concerned the low pressure fuel oil supply line from the fuel oil filter to the engine fuel oil supply header on the emergency diesel generators.
During testing and inspection activities for Division I and II standby diesel generators it was observed that the low pressure fuel oil supply line vibrated excessively.
In the Division I diesel 2EGS"EG1, two hold down clamps were damaged and subsequently a pin size leak developed in the fuel line.
In the case of the Division II diesel 2EGS*EG3, surface damage was observed on the fuel line at a point where it came in contact with a 1 inch tube line.
The recommended corrective action, provided by the diesel generator manufacturer, was to replace the existing clamps on the fuel line with clamps of a modified design.
The inspector.verified the modified fuel line clamps have been installed as stated in the corrective actions, the damaged portion of the fuel line was replaced, and flushing, inspection, and testing were performed as required.
This item is closed.
6.0 Unresolved Items Unresolved Items are matters about which more information is required to ascertain whether they acceptable items or violations. Unresolved items are discussed in paragraph.
7.0 Mana ement Meetin s
Licensee management was informed of the scope and purpose of the inspection at the entrance interview on August 11, 1986.
The findings of the inspection were discussed with licensee reprentatives during the course of the inspection and presented to licensee management at the August 15, 1986 exit interview (see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the inspectors.
The licensee indicated that no proprietory information was involved within the scope of this inspectio Number Revision AP 1.2
AP 3.4.3
~
QAP 10.03
QAP 10.30
QAP 16,03
QA'I 10.30.10
AT'TACHMENT A Title Composition 'and Responsibility of Unit Organization Production and Control of Procedures Administration of Technical and Safety Reviews, Safety Review Panel Procedure for Modification and Addition Procedure for Modification and Addition Unit 2 Procedure for Preoperational Tests QA Department Surveillance Activity QA Department Inspection activities Corrective Action Requests (CARs)
NMPC QA Receipt Inspection of Spare and Replacement Parts TDP 8
Post Maintenance Testing Criteria N2-ISP-SWP-R104 (Interim)
Operating Cycle Channel Calibration of Service Water Pump Discharge Bay Level High In'strument Channel Modification Package No. 83-87 data sheets for test procedures N1-EPM-V5, N1-ISI-HYD-01 & 05/39, N1-ISP-25.2 8( C-24.4, N1-ST-R8 8( 12
Inspection Summary Report Date 1.
General Plant
~c Report 0 ro
g Accompl. Insp ctors Date Inspection Completed Lead Inspector Ju'CC2-Z 2.
Inspection Scope ~~
hlodules ~w- ~WP(%C) DC3ozX(%C)~92 ol (%C)~ZS urY(%C) 2 17eM(%C)
Areas Inspected
~~sw Ct~
3.
Inspection Results Violations Unresolved Items Status of Open Items Reviewed C'
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cPZ- 0/-0 ( oi re
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C -2'n Al-2V-d /
Problem/Controversy Areas 7~a'ce~~
8'.
Miscellaneous Overall SALP Rating 5 Basis
7 4f Independent Meas./ Calc.
5, Innovation'A Area Review)
5.
Documentation:
Cover Letter
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