ML20235H103
| ML20235H103 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/07/1986 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | Linville J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20235G041 | List: |
| References | |
| FOIA-87-438 NUDOCS 8709300375 | |
| Download: ML20235H103 (3) | |
Text
e D
DATE: 11-7-86 TO:
Jim Linville, Chief, Section 2C, DRP FROM:
NMP Resident Office WEEKLY STATUS REPORT - NINE MILE POINT 2 1.
Plant Status:
1 As of 7:00 AM, November 7, 1986, the licensee has loaded 249 fuel bundles.
Fuel loading has progressed smoothly with only minor difficulties. The resident inspectors and a region based inspector conducted round-the-clock coverage for the first three days of fuel load.
Upon receipt of the low power license on 10-31-86, the licensee conducted a reverification of Technical Specifications and reassessment of readiness to load fuel. The Station Operations Review Committee (SORC) convened on 11-1-86 and recomg9nded proceeding with fuel load.
~
Concurrent with the final SORC review, the licensee attempted to install the four neutron sources. The tool used for installing the source pins was found to be the wrong size.
A similar tool was flown in from Limerick Station, but it was also found to be improperly sized. The Limerick tool was used to grapple the source pins and lower them to the top of the core, however, divers were used to position and lock the source pins into the upper core plate.
The first fuel bundle was loaded in the core approximately 8:45 AM, November 2,1986. The media was allowed access to the refuel floor for the initial core
~~'
loading.
2.
MSIV Status:
As of November 7, two of the four remaining MSIV balls to be refurbished have completed the Haynes 25 underlay coating process and are at Union Carbide for application of the tungsten carbide overlay. The remaining balls are still in the Haynes 25 underlay repair process. A target date for final MS1V repair and assembly is 11/24, pending resolution of a licensee request for relief from ASME Section XI nondestructive examination requirements for the MSIV ball underlay repairs. Subsequent liquid dye penetrant testing of Forn 939 8709300375 870924 PDR FOIA PDR WETTER HB7-438
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the Haynes 25 weld repair indicate additional circular-shaped surface flaws. The licensee contends that these flaws do not adversely impact the structural integrity of the tungsten carbide overlay and do not require grind out and repair.
l Vendor testing of a completely modified MSIV actuator was performed satisfactorily. Actuator modification of all MSIVs is incorporated in 11/24 target completion date.
3.
Equipment Problems:
Aside from the above mentioned neutron source pin installation tool problem, the licensee has had only minor equipment problems.
On 11/1, while making final preparations for fuel load, SRM channel A was found
__ inoperable.
The cause was determined to be a loose solder connection in the preamplifier high voltage pgwer supply.
On 11/2, the drive cable to the SRM D positioning mechani,sm snapped and will require replacement.
The detector was manually inserted. On 11/3, the electrical cable to the hoist grapple position switch was severed and required repair. On 11/5, the licensee started experiencing grapple hoist motor trips on overcurrent.
The problem is intermittent and has been traced to the grapple hoist control circuit. Fuel loading has continued and the faulty control-circuit card will be replaced in the near future.
4.
Reportable Events:
While conducting initial fuel loading, at 12:41 PM, 11/5/86, Intermediate Range Neutron Monitor (IRM)
Channel D spiked to the HI HI trip setpoint on Range 1.
No similar deflections were observed on the other neutron monitors. The spike was apparently caused by the bumping of a fuel bundle as it was being lowered into the core. The bundle location was in close proximity to the Channel D IRM.
Shortly after resetting the scram, a Scram Discharge Volume HI level l
trip was received. The licensee made an ENS call at i
approximately 1:30 PM.
)
On 11/6, the licensee security force determine that a vital area had been breached without proper compensatory action taken.
The licensee made an ENS call at 7:00 PM, 11/6, to report the event.
5.
Planned Activities:
After the completion of loading the first 362 fuel assemblies, the licensee will conduct a Partially I
3
4 o
e p
i Loaded Shutdown Margin Verification in accordance with the Open Vessel Start-Up Test Program. This test is scheduled for 11/8.
6.
Violation of Technical Specifications:
On November 3, 1986, while conducting the Reactor Mode Switch surveillance test in preparation of resuming fuel load, the licensee violated Technical Specification (TS) 3.3.6 for control rod block instrumentation. The surveillance procedure required that no rod blocks be in effect during the test. At the time, SRM channel B was indicating approximately 3 CPS (above the downscale rod block setpoint) and the other three SRM channels were reading downscale. To satisfy the. surveillance prerequisites, the operators bypassed all four SRM rod block functions in accordance with jumper / bypass control procedures. During the subsequent administrative review of the jumper / bypass control documentation on 11/6, the licensee recognized the violation of TS 3.3.6 and Table 3.3.6-1.
This TS requires that a minimum of 2 SRM downscale rod block instrumentation channels be operational in Mode 5 (Refueling). With all the SRM downscale rod blocks inoperable, the licensee was in a Limiting Condition for Operation (LCO) which requires that at least one channel be placed in the tripped condition within one hour.
This was not done, as the SRM downscale rod blocks were bypassed for approximately two and one half hours. Had the licensee not jumpered SRM Channel B, this would have placed them in a less restrictive seven day LCO.
cc:
T. Murley J. Allan W. Kane S. Collins R. Gallo S. Eb neter T. Martin 0
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