IR 05000220/1979022
| ML17053B205 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/26/1979 |
| From: | Architzel R, Mccabe E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053B198 | List: |
| References | |
| 50-220-79-22, NUDOCS 7911210402 | |
| Download: ML17053B205 (18) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No.
50-220/79-22 Docket No.
50-220 License No. DPR-63 Priority Category Licensee:
Niagara Mohawk Power Corporation 300 Erie Boulevard West S racuse, New York Facility Name:
Nine Mile Point Station, Unit
Inspection at:
Scriba, New York Inspection conducted:
August 2 -24, 1979 Inspectors:
R. Architze
, Reactor Inspector te signed date signed Approved by:
E.
C. McCabe, Jr., Chief, Reactor Projects Section No. 2, R08NS Branch date. signed e fee.hv date signed Inspection Summar
Ins ection on Au ust 21-24, 1979 Re ort No. 50-220/79-22 Areas Ins ected:
Routine, unannounce
~nspectson y a NRC region-based inspector 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> of facility operations, diesel generator control circuits, and licensee action on previous inspection findings.
The inspection began during off normal hours (10:15 p.m., August 21, 1979}.
A facility tour was conducted.
Results:
Noncompliances:
One (failure to follow protective clothing require-ments of RWP, paragraph 3.c}.
Region I Form 12 (Rev. April 77}
DETAILS Persons'Contacted
't The following technical and supervisory level personnel were contacted:
M. Bandla, Shift Supervisor K. Dalbert, Supervisor - Electrical Maintenance E.
Duda, Assistant to General Superintendent J. Earls, Shift Supervisor E.
Leech, Supervisor - Radiochemistry and Radiation Protection
"T. Perkins, Station Superintendent
"J.
Shea, Assistant Operations Supervisor M. Stancliff, Shift Supervisor
"present at the exit interview.
Other licensee employees were also interviewed.
Licensee Action on Previous Ins ection Findin s (Closed)
Unresol ved Item (220/79-18-01):
Drywel1 Housekeeping.
Procedure Nl-OP-43, Startup and Shutdown, was revised (Revision 12, June 1,
1979)
to require documentation of satisfactory Drywell Housekeeping on the Primary Containment Pre-Startup Checklist.
(Closed)
Unresolved Item (220/78-21-04):
Diesel Generator Air Start Valves.
Procedure Nl-OP-45, Emergency Diesel Generators has been revised (Revision No. 4, June 5, 1979) to require locking of the air start valves to the diesels.
(Closed)
Unresolved Item (220/78-21-02):
The inspector reviewed the renewed license, dated December 19, 1978, for the SRO in question.
Review of Plant 0 erations a o Off Shift Ins ection The on site inspection began at 10: 15 p.m.
on August 21.
Required security force and operator manning were verified.
Plant conditions and control room annunciators were discussed with Control Room personnel.
No inadequacies were identifie b.
Shi f t 'o s 'and'0 eratin 'ecords The inspector reviewed the records listed below for compliance with the licensee's administrative procedure for Operations Department Logs.
(1)
Station Shift Supervisor's (SSS)
Log for the period July 5-22, 1979 (Log Book No. 233}.
(2)
Control Station Operator's (CSO)
Log for the period July ll -August 11, 1979 (Log Books Nos.
249, 250).
(3)
Jumper and Lifted Lead Log for all active entries.
(4)
Station Shift Supervisor Instructions (SSSI) for the period July 1 - July 30, 1979.
(5)
Operations Daily Checks (Nl-ST-DO) for the period July 1-28, 1979.
(6)
Operations Shiftchecks (Nl-ST-SO) for the period July 1-10, 1979.
(7)
Occurrence Reports (Not Resulting in LERS)
No.
'Date
'sub ect'9-36 8/4 Lo Lo Lo Hater Level Indicator Meter Stuck.
79-35 8/2.
79-34'/28 79-31 7/2, 79-29 6/16 79-26
'/4 Low Fish Impingement (Telephone to NRC 8/3}.
MS Radiation Monitor 8111 Recalibration Low Fish Impingement (Telephone to NRC 7/2)
Test Procedure
- Diesel Start Misinterpre-tation Low Fish Impingement (Telephone to NRC
'/4)
79-25 79-17 6/1, 5/9 Electromatic Relief Valve 8121 Failed to Operate (Pressure Sensor Inoperative)
Refuel Mode Low Fish Impingement (Telephone to NRC 5/9).
The licensee had recently increased unit output to 94K, up from the 90.5X limit with one recirculation pump inoperable required prior to Amendment 34, effective August 10, 1979.
Because the unit was being operated with one recirculation loop isolated, the inspector queried various operators and staff personnel concerning what actions would be taken if three loop or less operation were to occur (example:
one of the four running recirculation pumps tripped).
The answers received varied.
Technical Specifications are not specific about requirements with less than four loop operation.
The licensee stated that, until license conditions in this area are clarified by license amendment, the plant will be
'perated within the following restrictions:
(1) If at least four recirculation pumps are not operable, a
shutdown shall be commenced immediately and the plant placed in at least hot standby in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(2)
A recirculation pump shall not be stared, in the power operating condition, unless four other recirculation pumps are running.
(3)
The reactor shall be shutdown prior to'ntentional removal from service of more than one recirculation pump.
(This provision was made to prohibit intentionally going to opera-tion on 3 recirculation pumps while at power).
These restrictions were incorporated in Nine Nile Point Standing Order Number 18, Recirculation Pump Operation, dated August 23, 1979.
The inspector stated that this item will be followed (220/79-22-01) until incorporated into permanent station proce-dures or the Technical Specifications are revised concerning recirculation pump operation.
Plant Tour The inspector observed control room operations and conducted a
facility tour accompanied by a licensee representative.
The tour included the Reactor Building, Turbine Building and the Diesel Generator Rooms.
The following were among the items observed:
Radiation Controls properly established; No fluid leaks of significance; Control Room manning in accordance with Technical Specifica-tions; Piping vibration not excessive;
Reasons for lighted annunciators in the Control Room; t
Housekeeping, including examination for fire hazards; Positions of Selected Locked Valves; and, Equipment Tagging.
During the tour, the inspector took the readings for 'the Daily Checks (Nl-ST-DO), April 16, 1979 revision.
.
The following items were checked by instrument observations:
Liquid Poison Tank:
12.78K concentration (sampled within last 30 days),
3600 gallons, 90'F, agreed with TS Figure 3.1:2a Emergency Cooling Tank (a)
Shell Mater Level ill and 112:
7.5 feet (min. 6.5 feet)
121 and 122:
7.5 feet (b)
Make-up Tank Level ¹ll 8.2 ft.
(Min. 8 ft.)
¹12 8.2 ft.
Reactor Coolant Leakage (a)
Excess Flow Alarm No (b)
Unidentified (limit 5 gpm)
1.18 gpm (Floor Drains)
(c)
Identified 3.8 gpm (Limit = 25 minus unidentified gpm) (Equipment Drains)
Torus (a)
Downcomer Submergence (b)
Temperature (Mater)
(c)
Torus Pr'essure (Temperature agreed with TS Figure 3.3.3a for existing submergence)
Reactor Vessel Mater Level Alarms (Low Low)
10 Level Instruments (Including Yarways)
4.3 ft.
F
.44 psig No Agreement (Different Ref.)
Parameter Reactor Protective System:
Channel B
Guide Value and D
Units Main Steam High Flow (A, G, E,
C)
,Main Steam High Flow
.=(B,'H. F, D)
Reactor High Pressure (A, B, C, D)
Drywell High Pressure (A, B, C, D)
Reactor High Level (A, B, C,
D)
Reactor Lo Lo Level (A, B, C, D)
40 1040 1. 50
78
41 1030 1. 51
.77
38 1050 l. 58
78
+4 psid
+4 psid 1050
+24 psig 1.60
+.1 psig
+4 inches
+2 inches Reactor High High Pressure 1040
~
~
(A,B,C,D)
Reactor Lo Lo Lo Level 213 (A, B, C, D)
Emergency Cooling DNSC High Steam Flow (A, B, C, D)
(DNSC = Downscale)
1030 212.
1040 232 DNSC 1025 psig 235
+3 inches DNSC
+4 inches The inspector questioned the guide value discrepancies for the Reactor Protective System readings.
The licensee stated that an error had been made and that the guide value tolerance only ap'plied to comparisons between channels A to B and C to D.
A draft procedure change was reviewed by the inspector specifying this application of guide value tolerances.
This item is unre-solved pending revision of the Daily Checks (Nl-ST-DO) (293/79-22-02).
During the tour of the reactor building (237 elevation),
the inspector observed a worker lying on a table in a posted con-taminated high radiation area.
The worker was dressed in street clothes, and not the protective clothing specified on applicable Radiation Work Permit No. 6442.,
The worker left the area and was surveyed by the Health Physics staff with no contamination found on his person.
The inspector stated that failure to adhere to the protective clothing requirements of the RWP was an item of non-compliance (220/79-22-03).
4.
Emer enc Power Sources Diesel Generators The inspector reviewed the starting circuitry for the diesel genera-tors in order to determine which engine/breaker trips are bypassed during LOCA (Loss of Coolant Accident) situations.
The drawings reviewed were C-19410-C, Elementary Wiring Diagram, 4. 16KV Emergency Power Boards and Diesel Generators 8102 and 0103-Control Circuits Sheet 1 (Revision 10), Sheet 3 (Revision 11),
and Sheet 10 (Revision 6).
The diesel engine starts automatically upon a sensed undervoltage condition on their respective 4.16 KY power boards, only.
The Diesel Engines trip upon low cooling water level, low bearing oil pressure, and overspeed.
The output breaker trips upon overvoltage, directional ground, and differential overcurrent.
In addition, the diesel generator locks out if the engine does not reach preselected speeds at certain points in the starting sequence.
The overspeed, low water level, and the bearing oil pressure switches are bypassed for two minutes if the engine is started by a sensed undervoltage.
No unacceptable conditions were identified.
5.
NRC Re ort Review a.
NRC:RI in office review of the foll'owing LERs has been completed.
LER
"79-018
"79-015 79-014 Dated August 10, 1979 June 28, 1979 June 15, 1979
~Sub 'ect Vacuum Switch (Vacuum Relief System) Setpoint Drift Time delay relay Setpoint Drift Core Spray Snubber Inoperable
"79-013 79-010 79-009 79-008 79"006 79-005 79-004 79-003 June 12, 1979 May 23, 1979 June 5, 1979 June 5, 1979 May 10, 1979 April 30, 1979 April 19, 1979 April 4, 1979 Temporary Procedures not Reviewed within Seven Days Vacuum Relief Valve Failed Leak Rate Test Maintenance Procedure not Reviewed within Seven Days Containment Spray Heat Exchanger Failed Leak Rate Test Over frequency Relay-MG Set No.
172 Setpoint Drift Containment Isolation Valves Failed Type C Leakage Tests Diesel Generator Inoperable Containment Isolation Valves Failed Type C Leakage Tests
"These LERs were also reviewed onsite.
The inspector stated that the subject LERs were not sufficiently descriptive of the particular events and that in the case of LER 79-013 the cause code, cause subcode, and action taken blocks were incorrect.
These three LERs remain open pending resubmission by the licensee of updated LER's"'(unresolved item 220/79-22-04).
b.
NRC:RI in office review of the following reports has been com-pleted with no unacceptable conditions identified:
February, 1979 Monthly Report (NMPC letter dated March 8, 1979)
March, 1979 Monthly Report (NMPC letter dated April 9, 1979)
April, 1979 Monthly Report (NMPC letter dated May 10, 1979)
May, 1979 Monthly Report (NMPC letter dated June 8, 1979)
June, 1979 Monthly Report (NMPC letter dated July 10, 1979)
6.
Unresolved Item An item about which more information is required to determine accept-ability is considered unresolved.
Paragraphs 3.c and 5.a contain unresolved items.
7.
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 item of noncompliance and unresolved items were identified.