IR 05000220/1980014
| ML17053C254 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/10/1980 |
| From: | Chung J, Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053C252 | List: |
| References | |
| 50-220-80-14, NUDOCS 8101300019 | |
| Download: ML17053C254 (18) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
0
. ~50-22 80-1 Docket No. 50-220 Region I License No.DPR-63 Priority Category Inspection co ucted:
r Inspectors:
Oct er 14-17, 1980 W.
Chung, eac pector clear Support ec on No.,2, ROSNS Branch Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard.West Syracuse, New York 13202 Facil ity Name Nine Mi1 e Point Nucl ear Station, Unit
Inspection at:
Scriba, New York 1/-ro-P~
date signed date signed Approved by:
C E.
G. Greenman, Chief Nuclear Support Section No. 2, ROSNS Branch date signed JJ-zc - S>
date signed Ins ection Summar
Ins ection on October'14-17 1980 (Re 'ort No. 50-220/80-14)
Areas Ins ected:
Routine, unannounced inspection by a region-based inspector of fo ow-up on prior identified items; administrative controls for surveillance procedures; surveillance testing; inspector witnessing of surveillance tests; technician qualification; and control room'and facility tours.
The inspection involved 22 inspector-hours onsite by one NRC region-based inspector.
'esults:
Noncompliances:
None.
Region I Form 12 (Rev. April 77)
~4mee Q)R,
DETAILS 1.
Persons Contacted Princi J.
N.
- M. C.
N.
C.
D.
E.
- T. M.
'*J J
M. A.
B.
E.
al Licensee Em lo ees Duell, Supervisor, Chemistry and Radiation Protection Drews, Superintendent, Technical Services Hendrick, Dosimetry and ALARA Coordinator Neild, Station Shift Supervisor Roman, Station Superintendent Shea, Assistant Operations Supervisor Silliman, Technical Superintendent Taylor, IKC Supervisor USHRC
'.
0.
Hudson, Resident Inspector Other licensee employees were contacted during the inspection.
These included engineering personnel, administrative personnel, reactor operators, health physics personnel, and technicians.
- Denotes those present at exit interview.
e 2.
Licensee Action on Previous Ins ection Findin s
(Open) Unresolved Item (220/78-03-01):
The following items required procedural changes.
The inspector reviewed the following procedures to verify that the changes had been completed.
Results were as follows:
a 0 Procedure Nl-ST-C5 "Secondary Containment Leak Rate and Reactor Building Ventilation Operability Test" specified obtaining data from the computer when the actual data must be gotten from local gauges.
Also, the procedure required recording the data in PSID although the data was taken in inches of water.
Revision 3 of the procedure Nl-ST-CJ was issued on February 1,
1979, reflecting actual source of the data and the data readings.
This procedural part of the above item is closed.
b.
The acceptance criteria of Suppression Chamber Mater Temperature, Primary Containment Pressure, and Downcomer Submergence are not clearly spelled out for the verification of compliance with Technical Specifications.
The procedure Nl-ST-DO,."Daily Checks,"
Revision 5, February 21, 1980, included the acceptable numerical values for the Suppression Chamber Mater Temperature, Primary Containment Pressure, and the Downcomer low and high submergences in conformance with the Technical Specifications.
This procedural part of the above item is close C.
Two different values for minimum diesel fuel oil requirements were
'specified in procedure Nl-ST-M4, "Emergency Diesel Generators Manual Start and 1 Hour Rated Load Test."
The procedure had been revised on November 27, 1979 to correct the discrepancy, consistent with the
" Technical Specifications.
This procedural part of the above item is closed.
d.
Surveillance Test Procedure Nl-ST-M4 did not include a verification of the Diesel Fuel Oil Transfer Pump Operability Test.
The procedure was revised on June 12, 1978 for the test, but was deleted during a subsequent revision on November 27, 1979.
A licensee representative stated that the deletion of the test was due to a clerical mistake and the procedure was rewritten to include the operability test.
This procedural item is open pending review and approval of the onsite review committee and subsequent inspection.
e.
, Surveillance Procedure Nl-ST-01 did not contain provisions for monitor-
'ng the'erformance of the core spray pump motor cooler and the associated pressure control valve.
The procedure Nl-ST-01, Revision 3, had been revised on February 13, 1979 to include the use of a hand held Pyrometer in order to certify cooler operability.
This portion of the test was deleted from the procedure during a subsequent revision on February 5, 1980, because of a clerical error.
The procedure was rewritten to include the cooler operability test.
This item remains open pending review by the onsite review committee and subsequent re-inspection.
(Closed)
Unresolved Item (220/79-03-03):
PAID drawings C-18002-C, Sheet 1,
Revision 12, and C-18006-C, Sheet 1, Revision 2, both show the same portions of the head spray system with different identifications of the head spray valves.
Also, there was no station procedure which required drawings to be updated when differences between drawings and "As Built" conditions were discovered.
The inspector verified by review of PAID drawings C-1800-C, Sheet 1, Revision 14, December 10, 1979, and C-18006-C, Sheet 1, Revision 1, July 24, 1980, that the head spray valves were correctly labeled as CRD 709, 710, 711 and 712 in both drawings.
Also, Station Administrative Procedures APN-5, "Procedure for Control of Procedures, Instructions, Orders and Drawings," Revision 5, September 26, 1980, had been revised to include a provision in paragraph 4.2.6, which requires updating the drawings when a discrepancy is discovered.
Administrative Controls for Surveillance Procedures The inspector performed a review, on a sampling basis, of the following administrative procedures for conformance with Technical Specifications, Section 6, "Administrative Controls,"
ANSI N18.7-1972 "Administrative Controls for Nuclear Power Plants" and Regulatory Guide 1.33 "guality Assurance Program Requirements."
Administrative Procedure No. (APN)-1, Procedure for Administrative
.Controls, Revision 4, September 26, 1980.
APN"5, Procedure for Control of Procedures, Instructions, Orders and Drawings, Revision 5, September 26, 1980.
APN-6, Preparation of Procedures, Instructions and Orders, Revision 2, December 26, 1978.
APN-8, Test and Inspection Program, Revision 1, January 10, 1979.
APN-15, Procedure for Control and Calibration of Equipment Used in Tests and Inspections, Revision 1, April 25, 1980.
No unacceptable conditions were identified.
Surveillance Testin The inspector reviewed surveillance tests on a sampling basis to verify the following.
Tests required. by Technical Specifications are available and covered by properly approved procedures.
Test format and technical content are adequate and provide satis-factory testing of related systems or components.
Tests have been reviewed as required by Facility Administrative Requirements.
Tests were performed within the time frequencies specified by the Technical Specifications and appropriate action was taken for any item failing acceptance criteria.
b.
The following surveillance tests for the periods indicated were reviewed.
Nl-ST-M2, Emergency Cooling Systems Makeup Tanks Level Control Valves Exercise, Revision 3, April 10, 1980.
Data reviewed for tests performed April 7, May 9, June 6, July 7, and August 7, 1980.
Nl-RCPCP-10, Reactor Core Parameter Calculation Procedure-Minimum Critical Power Ratio, Revision 2, April 20, 1979.
Procedure reviewed.
Nl-RPSP-l, Reactor Physics Surveil]ance Procedure -'inimum Critical Power Ratio, Revision 5, October 19, 1980.
Data reviewed for fourteen tests performed October 1 through October 14, 198 Nl-ST-V3, Rod Worth Minimizer Operability Test, Revision 3, September 13, 1978.
Data reviewed for six tests performed July
.11, July 14, July 17, July 25, September 19, and September 21, 1980.
Nl-ST-W1, Control Rod Exercising, Revision 4, September 16, 1980.
Data reviewed for nine tests performed August 8, August 15, August 22, August 29, September 5, September 12, September 14, September 27, and October 4, 1980.
Operational Surveillance Test Nl-ST-DO, Daily Checks, Revision 5, February 21, 1980.
Makeup Tank Level Surveillance Data reviewed for fifteen tests performed September 20 through October 7, 1980; Suppression Chamber Water Temperature and Downcomer Submergence data reviewed for fifteen tests performed September 20 through
.
October 7, 1980.
Nl-ST"R2, Loss of Coolant and Emergency Diesel Generator Simulated Automatic Initiation Test, Revision 2, September 13, 1978.
Data reviewed for a test performed June 16, 1979.
Nl-PSP-1, Reactor Water Sampling and Analysis, NMP-l, Revision 3, July 29, 1980:
Conductivity and chloride test data reviewed for
.
fifteen tests performed September 10 through September 25, 1980.
Nl-ISP-RPS-TP, Reactor Protection System - Auto Trip System Instrument Trip Channel Test/Calibration, Revision 6, February 21, 1980.
(1)
Subsection 201.2/476, High Drywell Pressure.
Data reviewed for six tests performed April 26, May 24, July 19, August 16, and September 20, 1980.
(2)
Subsection 30-07, Reactor High Pressure Scram.
Data reviewed for five tests performed May 31, June 29, July 25, August 23, and September 20, 1980.
(3)
Subsection 30-08, High Reactor Pressure
- Emergency Cooling.
Data reviewed for seven tests performed May 9, May 24, June 6, July 3, August 1, September 6, and September 26, 1980.
Nl-ST-SAl, Smoke and Heat Detector Test, Revision 2, January 9,
1979.
Data reviewed for tests performed January 14 and July 9, 1980.
Nl-ST-SO, Shift Checks, Revision 5, January 29, 1980.
Data reviewed for thirty-five checks performed September 1 through October 1,
1980.
(Reference Findings Detail 4.c. 1)
e C.
~Findin n
Technical Specifications require availability of two gravity feed makeup water tanks for the Emergency Condenser.
The basis for this specification is to maintain a continuous system operation for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, providing approximately 72,000 gallons of makeup water.
The plant has two horizontally mounted and cylindrical tanks.
Each tank is 60 ft. long and ll ft. in diameter with a capacity of 40,000 gallons.
The inspector's review of Operational Surveillance Procedure Nl-'T-DO
"Daily Surveillance Checks".indicated the minimum makeup water level at 8 ft.
However, a review of the calibration curve for the water level versus volume showed that approximately 9 ft.
of water in each tank is required to provide 36,000 gallons of water and a total of approximately 72,000 gallons from two tanks.
The inspector further determined from the daily surveillance records for September 22 through October 7, 1980 that the makeup water tank levels had been consistently logged at less than 9 ft.
during that period.
Discussion with a licensee representative and review of P8ID drawing C-18579-C showed that the level transmitter was mounted outside of the tank and a connecting pipe leading to the trans-mitter was tapped from one foot above the tank bottom. Therefore, the licensee incorrectly assumed that 0 ft. indication would represent 1 ft. of actual water in the tank, and an 8 ft. indica-tion would correspond to 9 ft. of actual water level.
The inspector pointed out that the indicator's reference level should not be the location where the transmitter connector was.
tapped, one foot from the tank bottom, but where the level sen-sor/transmitter was positioned.
The inspector further demonstrated the validity of his position using a water-filled Tygon tube with authorization of and in the presence of a licensee representative that the level transmitters were exactly aligned with the tank bottoms, outside of the makeup tanks, demonstrating that the indicator readings were representing the actual water levels in the tanks.
The inspector also cautioned that the level sensor was incapable of monitoring the bottom one foot in the tank since the transmitter was connected from one foot above the tank botto The licensee acknowledged the inspector's findings and concern, and is taking the, following corrective acti'on.
(a)
Immediately maintaining the makeup water tank levels at
ft. or more as indicated on the Control Room Indicators.
(b)
Daily Surveillance Procedure Nl-ST-00 will be revised by November 1,
1980 to change the minimum acceptable makeup tank levels to 9 ft.
(c)
Control Room Level Indicator will be modified to monitor the full range of the tank level, i.e.,
11 ft.
This item is unresolved pending a subsequent re-inspection by
'RC:RI confirming completion of licensee actions.
(220/80-14-01)
(2)
An instrument calibration record performed September 19, 1980 for L8N Model 4988 Cohductivity Monitor had neither a signature of the technician who performed the calibration nor was there any objective evidence of data review.
A licensee representative stated that the Conductivity Monitor Calibration Procedure and data sheet would be revised by January 1,
1981, and would include the requirements for signing the calibration data sheet by the technician performing the calibration and supervisory review.
This item is unresolved pending subsequent reinspection in this area.
(220/80-14-02)
5.
Ins ector Witnessin of Surveillance Tests a.
Surveillance testing was witnessed to verify the following.
Required procedures were available, in use, and followed.
Special test equipment required by procedure was'alibrated and in use.
Test prerequisites were met and initial conditions were observed properly.
The procedure was adequately detailed to assure performance of a satisfactory surveillance tes b.
The following two surveillance tests were witnessed:
Nl"RPSP-1, Reactor Physics Surveillance - Minimum Critical Power Ratio Determination performed October 16, 1980.
Nl"ISP"RPS-TP, Reactor Protection System - Auto Trip System Instrument Trip Channel Test/Calibration, performed October 17, 1980.
No unacceptable conditions were identified.
6.
Technician ualifications The inspectors reviewed the qualification records of four currently assigned-technicians having responsibility for surveillance testing of safety related systems and components,'to ensure that the personnel qualifications met the minimum training and experience guidelines of ANSI N18. 1, "Selection and Training of Nuclear Power Plant Personnel."
7.
No unacceptable conditions were identified.
Control Room Observations and Faci,lit Tours a 0 The inspector observed control room operations for control room manning, shift turnovers, and facility operation in accordance with Administra-tive and Technical Specification requirements.
In addition, the inspector toured the Turbine/Reactor Buildings, Service areas, including the Cable Spreading Room, Emergency Batteries, Screen House, and the Diesel generator rooms.
Housekeeping practices, work in progress, radiation control measures, and general plant conditions, were observed.
b.
~Findin n
A survey meter, Model RM-3C, Serial No.
140, used to frisk personnel leaving radiation areas and entering the administrative building at elevation 277, was found to read a background counting in excess of 350 - 400 CPM.
A licensee representative stated that, the frisking surveyor would be shielded from the radiation sources of overpassing piping system to reduce the background countings to less than 200 CPM.
This item will be reviewed during a subsequent NRC:RI inspection.
(220/80-14-03)
8.
Unresolved Items Unresolved items are matters about which more information is required to clarify whether they are acceptable, items of noncompliance, or deviations.
Two unresolved items were identified and are= detailed in 4.c(l) and (2).
9.
Entrance and Exit Interviews Licensee management was informed of the purpose and scope of the inspection at the entrance interview, and the findings of the inspection were period-ically discussed.with the licensee representatives as summarized below:
Date October 14, 1980 October 15, 1980 October 16, 1980 Re ortable Details Covered Entrance Interview 4. c(1)
4.c(l), 4.c(2), 7.b October 17, 1980 The inspector conducted an exit (denoted in paragraph 1) at the findings of the inspection were 7. b, Exit interview with licensee representatives conclusion of the inspection, where the presented and acknowledged by the licensee.