IR 05000220/1979009
| ML17053A834 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/01/1979 |
| From: | Architzel R, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053A833 | List: |
| References | |
| 50-220-79-09, 50-220-79-9, NUDOCS 7907230479 | |
| Download: ML17053A834 (14) | |
Text
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II Docket No.
50-220 U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I License No.
DPR-63 Priority Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, New York Faci 1 ity Name Nine Mi1 e Point Station, Unit
Inspection at:
Scriba, New York Inspection conducted:
March 26-29, 1979 Inspectors:
Category C
- 3 R. Architzel, actor Inspector at s
ned date signed date signed Approved by:
E.
C.
McCa Jr.,
C ',
actor Projects Section N
. 2, RO&
Br h
date signed Ins ection Summar
Ins ection on March 26-29, 1979 Re ort No. 50-~20/79-09 Areas Ins ected:
Routine, unannounced inspection by one NRC regional based inspector, 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> o
refueling operations, IE Circular:and'Bull.etin'review; and licensee action on previous inspectionfindings.
A facility tour was conducted.
~N Region I Form 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted The following technical and supervisory level personnel were contacted:
E.
Duda, Assistant to General Superintendent
- Nuclear Generation
- T. Perkins, Station Superintendent R.
Raymond, Fire Protection Coordinator J.
Shea, Station Shift Supervisor
- C. Stuart, Supervisor Operations
- denotes those present at the exit interview.
Other licensee employees were also interviewed.
2.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresolved Item (79-21-06), include Safety Related Maintenance in Monthly Reports.
In January, 1979 the licensee started incorporating a major maintenance summary in the monthly report.
(Open)
Unresolved Item (78-21-05), Inclusion of Reporting Requirement Reference in LER Cover Letter.
Although reference is now being made to the Tech'nical Specification section, the particular requirement is still not identified.
The licensee stated that this will be done for future LERs.
3.
~Fili i a ~
Facility tours were conducted during the course of the inspection, both in the company of a licensee representative and by the in-spector alone.
Areas examined included the refueling floor, the drywell (all levels),
the torus (de-watered),
the control room, other accessible portions of the reactor, Radioactive Waste, and Turbine Buildings.
The inspector observed portions of the following refueling outage work:
Removal of a control rod (fuel had been removed from the reactor core)
In Service Inspection (via Underwater Camera) of the Core Spray Spargers
Installation of the Safety Relief Valve "Y" guenchers
'(Torus)
Installation of the Vent Header Deflector (Torus)
Installation of new Tie Straps for the-Vent Header Downcomers (Torus)
Work areas were observed for adequate housekeeping safety and fire hazards.
Radiation Protection practices and controls were inspected.
Positioning of selected components and conditions of shock suppressors was reviewed.
Three unresolved items were identified as described in paragraphs b, c, and d below.
Additional housekeeping and safety concerns were identified by the licensee's representative and corrected.
During the tour the inspector and a licensee representative examined automatic closing fire doors to ensure the problems identified in IEC 78-04, Installation Errors in Fire.Doors, did not exist.
While the particular problems did not exist, two of the doors (Offgas Building and T.B. 277'W Corner)
were in need of lubrication and did not slide closed on their own-when unlatched.
The doors may have closed in an actual situation because the installed weight would assist in closing.
The licensee took action to ensure these doors were properly lubricated and stated that the surveillance frequency for the doors would be increased.
This item is unresolved (79-09-01)
pending completion of the licensee's action and reexamination.
During a tour of the reactor containment (drywell) the inspector noted that a hydraulic shock suppressor reservoir was out of fluid.
The snubber (No. 40-HS-8 on the core spray system)
was subsequently removed from the system, tested and reinstalled following the completion of this inspection.
The licensee stated that this snubber had previously been tested satisfactorily during the current outage and that apparently a workman had knocked loose fittings on the fluid reservoir.
This item is unresolved pending NRC review of 'the operability test data for snubber 40-HS-8 (,79-09-02).
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d.
,During the conduct of the tour the inspector noted three distinct methods of labeling valves at the station.
These include using a metal tag with an Alpha Numeric (System Procedure No.), or a metal tag with a P 5 ID (Piping and Instrumentation Drawing) Number, and hand writing the valve description on a nearby wall.
The inspector expressed concern about the various labeling schemes.
The licensee stated the official method of labeling valves was the metal ID tags.
Labeling of valves is unresolved and will be reexamined in future NRC inspection (79-09-03).
4.
IE Circular Review The following IE Circulars were reviewed on site to determine that the circular was received by licensee management, a review for applicability was performed, and that further action taken or planned was appropriate.
No unacceptable conditions were identified.
a 0 b.
Circular 78-02, Pro er Lubricatin Oil for Terr Turbines There are no Terry Steam Turbines in use at Unit 1.
The licensee reviewed the lubricating oil usage and schedule esta-blished for components at the unit.
A computerized program has been established with Mobil Oil Company to periodically review and update all lubricants in use.
These actions were documented in an internal memorandum dated May 15, 1978.
Circular 78-04, Installation Errors that Could Prevent Closin of Fire Door s Mesker D and H Pyromatic door closers are used at the plant.
The licensee inspected the subject doors (documented by an internal memorandum dated November 17, 1978)
and verified that the installation errors were not affecting the doors at NMP.
During a facility tour three Pyromatic doors were observed by the inspector.
None of the doors had the problems identified in the Circular, however, two were inoperable for other reasons.
An unresolved item was identified in this area (see paragraph 3).
Circular 78-06, Potential Common Node Floodin of ECCS E ui ment Rooms at B>1R Fac i 1 it) es Each ECCS equipment room (corner room)
has its own sump and sump pump which is isolated from other sumps and the torus area.
The licensee documented review of this circular in a memorandum dated June 23, 1978.
Circular 78-09, Arcin of General Electric Com an NEMA Size
Contactor s The licensee reviewed installations of these contactors and determined that those in use were manufactured before GE started using oversized tip support bindings.
None of the affected contactors were in the NHP-1 storeroom.
These actions were documented in a memorandum dated August 18, 1978.
Circular 78-11, Recirculation Hotor-Generator Sets Overs eed Sto s
The actual overspeed stop settings were examined and found to be set at 100% of rated flow.
The Kf factor being utilized by the licensee corresponds to a scoop-tube set point calibration resulting in a maximum flow of 102.5/.
This is the lowest maximum flow curve incorporated in T.S. figure 3.1.7-1.
Since the actual maximum flow was less than that allowed by the Kf factor curve a conservative value of Kf was being used and no further action by the licensee was necessary.
These actions were documented in a memorandum dated August 18, 1978.
Circular 78-13, Ino erabilit of Hulti le Service Mater Pum s
The licensee documented review of this circular in a memorandum dated September 5, 1978.
The Service Mater Strainers do have differential pressure alarms.
NHP-1 has tempering gates to allow cross connecting plant discharge with lake water suction, thereby being able to raise inlet temperatures (procedurally used to maintain temperature greater than 35 degrees F).
Hain condensor back flow is utilized to minimize frazzile ice buildup at the lake intak g.
Circular 78-15, Tiltin Disk Check Valves The licensee documented review of this circular in a memorandum dated November 17, 1978.
The licensee stated that installed tilted disk check valves are designed for horizontal installation and installed horizontally.
HMPC Engineering personnel were contacted to make them aware of the potential problem.
h.
Circular 78-16, Limitor ue Valve Actuators The station reviewed the design and determined that two applicable valves (Shutdown Cooling Inner Isolation Valves) are installed at NMP Unit l.
A test was performed to verify that they would operate by the installed motor following manual closing and opening.
The valves are operated via the motor operator, with manual operation reserved for situations where the motor operator became inoperable.
This minimizes manual operation.
These actions were documented in a memorandum dated August 28, 1978.
Circular 78-18, UL Fire Test This circular was issued for information only and no specific action was requested.
The licensee, documented review of the issues addressed in the circular in a memorandum dated January 4, 1979.
NMPC has requested bids to evaluate the fire rating of NMP-1 electrical penetrations.
5.
IE Bulletin No. 78-14, Deterioration of BUNA-N Com onents in ASCO Solenoids The inspector reviewed the action taken on the subject bulletin and the licensee's response dated January 30, 1979.
A member of the plant staff has been assigned responsibility for the replacement program which is to be completed during the current refueling outage.
The inspector noted that following the initial replacement the licensee plans to replace one third of the disks every refueling outage.
The inspector questioned the licensee concerning how this would ensure that the BUNA-N Components did not exceed General Electric's determination of a seven year service life.
The licensee stated that the solenoids will be examined at the start of each refueling 'outage and any components whose elapsed time since curing would exceed seven years prior to completion of the next cycle would be replaced.
This Bulletin will remain open pending completion of the ioitial~ replacements'and establishment of the long term preventive maintenance progra.
NRC In Office Review
a.
NRC:
RI in office review of the following LERs has been com-pleted with no unacceptable conditions identified:
LER Dated
~Sub 'ect 79-01/03L March 13, 1979 Setpoint Drift, Rod Block Flow Comparator b.
NRC: RI in office review of the following reports has been completed with no unacceptable conditions identified:
January, 1979 Monthly Report (NMPC letter dated February 7, 1979)
7.
Unresolved Item An item about which more information is required to determine accepta-bility is considered unresolved.
Paragraph 3 contains unresolved
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items.
8.
Exit Interview At the conclusion of the inspection the inspector held a meeting (see paragraph 1 for attendees)
to discuss the inspection scope and findings.
The unresolved items were identifie l'iv)
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