IR 05000369/1980039
| ML20126F380 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 02/05/1981 |
| From: | Donat T, Graham M, Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20126F373 | List: |
| References | |
| 50-369-80-39, NUDOCS 8103120802 | |
| Download: ML20126F380 (8) | |
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ps n'ouq'o UNITED STATES f
(j. k~w,d;'T'tA'. j I't' "4 NUCLEAR REGULATORY COMMISSION REGION !!
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f 101 M ARIETT A ST., N.W.. SUIT E 3100 o
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AT t. ANT A, G E O RGI A 30303
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Report No. 50-359/30-39 Licensee:
Duke Fcwer Cmpany 422 South Church Street Cnarlotte, NC 28242 Facility Name: McGuire Nuclear Station Docket No. 50-369 License No. CPPR-33 Inspection at M:Guire Nuclear Station Inspectors:
M J. Granam Date Signed T. J. Dona t Date Signed s
Approved by:
(
')M M 2/$ /$r C. A. au!ian, Acting Secticn Chief Date Signed RONS Branch SUMMARY Inspection on November 1-30, 1930 l
Areas Inspected This routine announced inspection involved 183 resident inspector hours on site in the areas of Preoperational a n d i, t a r *.u p Test Procedure review, test witnessing, test results review, followup on previcus inspection findings
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and touring of plant to cbserve l' ensee activities.
Results
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Of the five areas inspected, no items of noncompliance or deviations were identi fi ed.
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810s120 gr
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-DETAILS
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1.
Persons Contacted i
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Licensee Employees
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M. D. McIntosh, Station Manager G. W. Cage, Superintendent of Cperations
D. J. Rains, Superintendent of Maintenance '
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T. L. McConnell, Superintendent of Technical Services
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W. M. Sample, Licensing & Project Engineer
D. Lampke, Assistant Licensing & Project Engineer
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l B. Hamilton, Reactor Engineer
M, Pacetti, Test Engineer
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D. Marquis, Assistant Reactor Engineer W. Messer, Assistant Electrical Engineer
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M. Glover, Station Emergency Preparedness Coordinator
T. Keane, Station Health Physicist i
Other licensee employees contacted included technicians, security force members, and of fice personnel.
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Attended exit interview
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2.
Exit Interview
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l The inspection scope and findings were summarized on 11/5/80 and
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12/3/80 with those persons 1-dicated in paragraph
above.
The
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inspectors summarized the areas examined and identified those items j
requiring futher examination at later times.
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I In the December 3 exit interview, the licensee and inspectors discussed the licensee's plans to preoperationally test the loose parts monitor.
The FSAR commits the licensee to install and test the system, although operability prior to fuel load is not a
specifically stated
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requirement.
Due to d> mage during later stages of construction, major i
l portions of the loose parts monitoring system must be replaced.
The licensee is concerned that further damage could occur if reinstallation is done while construction work is being done in the area -
The j
inspectors agree that the earliest need for the system is at the time
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l the reactor coolant pumps are first started after fuel loading.
The licensee has committed to completing preoperational testing of the
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l loose parts monitoring system prior to starting the pumps. Review of
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i completion of testing by that time is inspector followup item 80-39-01.
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3.
Licensee Action on Previous Inspection Findings
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Not inspected.
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i 4.
Unresolved Items Unresolved items were not identified during this inspec+. ion.
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5.
Procedure Review i
l Procedures were reviewed in the following arqas:
a.
Initial Fuel Loading l
The inspector reviewed the following procedures for completeness
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i in meeting Technical Specification conditions and surveillance requirements, and for compliance with industry practices.
TP/1/A/2650/01 Initial Fuel Loading CP/0/A/6550/04 Fuel ard Component Handling
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~0P/0/A/6550/07 Preparation for Refueling j
OP/0/A/6550/02 Overhead and Fuel Hancling Cranes Operation
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The inspector also verified the existence of a surveillance program for
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i the overhead crane hooks.
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l Two items remain open in this area, related to IE Circulars.
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(1) CI-80-21 Refueling Crew Makeup.
In NRC's response to Duke's l
letter of October 20, 1950 on IE Circular 80-21, NRC agrees that j
the Oconee organization of refueling crews meets the Technical Specification requirements.
The licensee indicated that the following changes to TP/1/A/2550/01 will be made-prior to fuel load so that the McGuire procedures reflect the acceptable
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refueling organization.
(a) The individuel operating the fuel handling bridge will be a e
licensed reactor operator, or a reactor operator in training l
being supervised by a
licensed operator on the refueling
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deck.
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(b) Clarification will be made of the -duties of the control room (
reactor operator during refueling.
Specific areas include
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normal duties a statement of permitted concurrent duties, if any, and duties assumed if tne ORD in cnarge of refueling
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leaves the control room.
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This circular remains open pending completion of these changes.
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(2) CI-80-13 Grid Strap Damage in Westinghouse Fuel Assemblies.
This circular includes several recommendations for loading fuel to e
avoid bundle contact.
The inspector concurs with the licensee's l
decision not to incorporate these recommendations into the initial
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fuel load procedure.
However, the licensee has agreed to reconsider the recommendations for refuelings, when some of the fuel bundles will be radiation deformed and problems with bundle
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to bundle contact are more likely.
This circular remains open
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until the refueling procedures are completed ar.d reviewed.
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b.
Precritical Testing l
The following test procedures were : reviewed' against the licensee's commitments stated in FSAR section 14.1, 7.1, 7.2, and 7.3; Reg Guides.1.68 and Reg Guide-1,33.
Specific items which; were verified included:
(1) Acceptance Criteria consistent with Test Specification and-FSAR_ description (2)
Procedural steps have provisions for completion signoffs (3) Data sheets are properly referenced -in the test, have provisions for all data requested, and are consistent with acceptance critaria (4) All changes have been approved by at. lea st the test director:
and his supervisor.
TP/1/A/1150/04B Pressurizer Functional Test TP/1/A/1450/07 Loss of Instrument Air Test TP/1/A/1550/04A Initial Core Assembly Insert Verification TP/1/A/2150/01 NC Flow Test TP/1/A/2150/02 NC Flow Coastdown Test TP/1/A/2150/03 Dynamic Rod Drop Test TP/1/A/2600/03
. Ir. core Thermocouple and RTO Cross Calibration TP/1/A/2600/04 Rod Position Indication Alignment TP/1/A/2600/06 Full-Length Rod Drive Mechanism Timing Test TP/1/A/2600/07 Full-Length Rod Control Cluster Assembly Drop Timing TP/1/A/2600/03 RTD Bypass Ficw Verification The inspector had no comments on the procedures reviewed.
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Zero Power Physics Testing The following procedures were reviewed for technical content and completion of FSAR requirements and commitments.
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TP/1/A/2650/02 Initial Criticality TP/1/A/2100/02 Zero Power Physics Controlling Procedure TP/1/A/2150/03A-H Boron Endpoint Measurement TP/1/A/2150/06A RCCA Pseudo Ejected Rod Test TP/1/A/2150/10 Stuck Rod Worth Measurement TP/1/A/2150/11A-E Isothermal Temperature Coefficient of Reactivity TP/1/A/2150/12A-E Zero Power Flux Map l
f The inspector has no further questions in this area.
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d.
Power Ascension Tes' ting
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The inspector reviewed TP/1/A/2150/06B Pseudo Rod Ejection Test for 30% power and has no further questions at this time.
6.
Test Witnessing-
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Portions of the following preoperational tests were observed.
TP/0/A/1450/02 Preoperational Filter Test for the Auxiliary Building Filtered Exhaust Filter Trains
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TP/1/A/1600/02 Nuclear Instrumentation Functional Test TP/1/A/1600/03 Reactor Protection System Functional Test
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The satisfactory completion of the applicable test prerequisites, procedure step >ignoff upon completion, and verification of test data meeting acceptance criteria were observed.
The activity area was clear
of adverse inspection findings.
In addition, the inspector observed the licensee's second preparatory
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emergency drill on November 5, 1920, and attended the post drill critique at the Training Center.
Particular items raised in the j
critique were division of responsiblities between the offsite and on
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site response teams, and changes to the data presenation to improve realism.
Necessary changes were planned prior to the December 5-6 planned drill.
The inspector also noted some communications problems at the site, mainly caused by relocation of the staff in the adnini-stration building while construction of the technical support center was in progress.
These problems are expected to be solved by completion l
of the TSC.
Further inspector observation was planned for the December f
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drill.
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Test Results Review
The following completed preoperational test packages were reviewed:
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TP/1/A/1200/04 Containment Spray Functional Test-TP/1/A/1600/02 Nuclear Instrumentation System Functional Test
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The review included verifying that:
.s j (a) all prerequites and system status items had been signed.
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(b) all change notices to the procedures had been reviewed to determine whether they were safety-related and had been properly approved i
before implementation.
(c) All procedural steps had been signed and dated.
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(d)
the final data package included at least the signed procedure,
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copies of all procedure. changes, copies of, all deficiencies and their resolution, and the test log.
(e)
all data-had been recorded and evaluated agains; the acceptance criteria and found acceptable,
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The inspector discussed with licensee personnel the acceptance cri te -ia of TP/1/A/1600/02 and method of calculating axial flux difference.
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Inspector comments are to be incorporated in the more extensive -nuclear
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instrumentation system calibration functional test, PT/0/A/4600/14, now
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being prepared. The inspector has no further questions in this area.
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S.
Fcilowup en Open Items f
i The following inspector followup items are nori closed.
a.
IFI-78-3E-07 Review of health pnysics, security and emergency plan training.
The inspector completed the licensee course s, noti ng that the lectures included plant specific alarms.
This-item is not closed.
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b.
IFI-78-16-05 Review of Operations staffing to veri fy receipt-of licenses.
Based on discussiors with the licensee, the inspector j
concluded that a sufficient number of individuals are licensed to
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meet staf fing requirements. This item is closed.
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c.
LII-80-10-03 Inadequate cards in Westinghouse Process Control
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System 7300.
The completion of the preoperational test program on
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Unit #1 and specifically the Reactor Protection system and Emergency
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Safeguards System interlock tests verifies that the Westinghouse 7500 Series process controller is functional.
This -item is
closed.
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d.
LII-80-10-06 Pressurizer PCRV Block Valve Operator torque inadequate.
The inspector reviewed NPR-1870A and w;rk requests 90699, 90734, 90735 and 90790 which replaced the valve internals and installed a more powerful actuator.
Based on the subsequent
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tests at the Marshall Ste.am Plant at McGuire the item is closed.
A e.
IFI-80-RD-34 NUREG-0660 Task Item III.D.2.4.a(2) Installation of fifty (50) environmental TLD's by IE.
The inspector verified by discussion with Region 11 that the TLD's were installed on
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July 22-24,1980. This item is closed.
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Plant Tours
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The inspectors made tours of the service building, auxiliary building,
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Unit '# 1 turbine building, and Unit #1 reactor containment observing licensee construction and preoperation activities.
Some areas of J
observation were:
(1) General plant cleanliness and housekeeping activities with specific attention to the various pump and heat exchanger rooms.
As the remaining portions of the plant are turned over to Steam Production, and the room access. limited to neces sa ry personnel,
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additional improvements in cleanliness will be both expected and achievable.
(2) Welding Fire Watches and Fire Extinguishers.. Checks were made for the presence o f.
welding fire watches and evidence of monthly inspections of fire extinguishers and hose racks.
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The activities associated with' the installation of the reactor vessei nead remote vent, tne reactor vessel tevei inoication system, anc tne containment hycrogen mitigation system.
Regior II requested that the licensee assure that there were no motor control center breakers ir. side of the ccatainment' which would have to be operated after a safety injection or in an accident scenario.
The licensee responded that there were none.
The inspector verified that there are none.
The inspectors identified no items of noncompliance in this area.
10.
Assistance to Regional and Headquarters Staff The Resident Inspector assisted in the November 17th visit to the McGuire Nuclear Station of Mr.
H.
R.
Denton, Director of NRR, Mr.
James P.
O'Reilly, IE Director Region II, and Mr.
R.
A.
Birkel, Licensing Project Manager for the M:Guire Station.
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The gentlemen arrived on November 16, 1980, and were briefed on the itinerary for the next cay.
On November 17 the group met with the Emergency preparedness Coordinators for four of the counties identified in the McGuire Emergency Pir Upon arriving at the site, the licensee made a formal presentation to the group concerning the preparation of Unit #1 for fuel loading.
Following a tour of the plant and the
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adjacent training center a press conference was held in the center's
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control room simulator.
The NRR Emergency Procedures Review g roup con si sti ng of three NRR engineers and four consultants were at the site during the month The resident inspector assisted the group in the initial evaluation of the procedures when used on the control room simulator, and the walkdown of the plant'.
b'embe r s of the NRR staff were also on site during November to discuss l
the cevelopment of fracture toughness data related to General Design f
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Cri terion 51.
The resident insp tor participated in th!
staff's examination of the installed location and condition of various components and systems.
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