IR 05000247/1979010
| ML19254D568 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/11/1979 |
| From: | Keimig R, Rebelowski T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254D566 | List: |
| References | |
| 50-247-79-10, NUDOCS 7910290088 | |
| Download: ML19254D568 (10) | |
Text
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-247/79-10 Docket No. 50-247 License No. DPR-26 Priority Category C
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Licensee:
Consolidated Edison Company of New York, Inc.
4 Irving Place New York, N.Y., 10003 Facility Name:
Indian Point Nuclear Generating Station, Unit 2 Inspection at:
Buchanan, New York Inspection conducted:
May 7 29, 1979 Inspectors
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F
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V. Rebelo(ski, Resident Inspector
'date signed T
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date signed
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cate signed Approved b
/[79 R.'R.KeimihChief,ReactorProjects date signed j
Section No. 1, RO&NS Branch Inspection Summary:
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Inspection on May 7-29, 1979 (Report No. 50-247/79-10)
Areas Inspected:
Routine, unannounced inspection to ve.rify that the licensee has taken the action required by IE Bulletins 79-06,79-06A and 79-06A Revision No. 1.
Specific areas of review included: operator training; valve / breaker / switch alignment procedures of engineered safety features (ESF); verification of valve / breaker / switch alignment for ESF; system operability following maintenance; plant surveillance test procedures; surveillance test results; pressurizer level trips; ESF operability following extended outages; licensee's utilization of independent verification; emeroency boiler feedwater system operability; and assessment of operating procedures.
The inspection involved 126 inspector-hours onsite by the NRC resident inspector.
Results:
No items of noncompliance were identified.
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Region I Form 12 (Rev. April 77)
7 9102 9008F
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DETAILS 1.
Persons Contacted A. Brescia, Instrument and Control Supervisor W. Carson, Test Engineer J. Curry, Nuclear Training Director A. Decker, Technical Engineer W. Ferreira, QA Engineer L. Kawula, Test and Performance Engineer C. Limoges, Reactor Engineer J. Makepeace, Technical Engineering Director W. Monti, Manager, Nuclear Power Generation Department A. Nespoli, Operations Engineer M. Shatkouski, Plant Manager T. Uhl, Training Instructor L. Volpe, Test Engineer The inspectors also interviewed other licensee employees including reactor operators and technical support personnel.
2.
Purpose This inspection was conducted to verify that the licensee has taken the actions required by IE Bulletins 79-06,79-06A, and 79-06A Revision No.1 relating to a review of their facilities and operations, and that the operators are aware of any procedural changes resulting from the Bulletins.
3.
Review of p erator Trainino The inspector verified that all licensed operators received the special NRC briefing on i.he events at the Three Mile Island Station.
Four operators who missed the briefing :onducted by the NRC on April 19, 1979, were briefed at a latter date by the resident inspector.
Additionally, the inspector verified the following by a review of training records and discussions with licensed operators on each shift.
(1) That operators received training for those procedure changes initiated as a result of Bulletins 79-06,79-06A, and 79-06A Revision 1.
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(2) That operators have been instructed on the specific measures which provide assurance that engineered safety features would be available if required.
(3) That operators have been instructed on measures to assure tnat automatic actuations of emergency safety features are not overriden except as procedurally permitted. The licensee's training simulator was programed to duplicate the incident of TMI-2.
Specific training was provided to operators for those systems discussed in the NRC bulletins.
(4) That operators have reviewed plant automatic actions initiated by reset of engineer-d safety features, that could effect the control of radioactive liquids and gases.
(5) That operators and supervisory personnel have been provided instructions for early NRC notification of serious events.
4.
Inspection of Engineered Safety Features (ESF)
a.
General An on-site inspection of the ESF systems was conducted which encompassed the following systems and components:
Safety Injection System
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Containment Spray System Residual Heat Removal System
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Containment and P.A.B. Cooling
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Isolation Valve Seal Water System
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Weld Channel and Containment Penetration Pressurization
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System Post Accident Hydrogen Removal System
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Diesel Generators Service Water System
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Closed Cooling Water System
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Component Cooling Water System Auxiliary Feed Water System 1221 2/3
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The specific areas inspected are as follows:
(1) Review of Valve / Breaker / Sjtch Alignment Procedures The inspecter performed a comparison of the valve / breaker /
switch alignment procedures against current alping and instrument diagrams and single-line diagrams for the previously mentioned ESF systems and components to verify their adequacy.
The following procedures were reviewed:
COL-5, Component Cooling Loop, Revision 5, August 30,
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1977 COL-12, Safety Injection - Containment Spray - Residual.
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Heat Removal Systems, Revision ll, April 11, 1979.
COL-13, Containme.it and PAB Cooling and Filtration,
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Revision 3, June 9,1977.
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COL-14. Isolation Valve Seal Water System, Revision 3, May 1, 1977.
COL-15, Weld Channel and Containment Penetration Pressurization,
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Revision 4, July 1, 1977.
COL-16, Post Accident Hydrogen Removal System, Revision
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4, January 31, 1977.
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COL-25, Diesel Generators (Jacket Water, Starting Air, Fuel Oil, Lube Oil) Revision 4, April 11, 1978.
COL-31, Condensate and Boiler Feed Pump Suction, Revision
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5, April 1,1977.
COL-33, Main and Auxiliary Boiler Feedwater, Revision
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5, April 11,1979.
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COL-36, Service Water and Closed Cooling Water, Revision 3, June 8,1977.
COL-51, Locked Valves, Revision 6, October 19, 1978.
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(2) Verification of Valve / Breaker / Switch Alignment for Accessible Components The inspector verified ESF systems valve / breaker / switch alignments by physically observing that valve, breaker, and switch positions were as required by the check-off lists associated with the procedures listed above.
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(3) System Operability Followina Maintenance Activities The inspector reviewed, for adequacy, the administrative controls imposed by the licensee to assure proper " return to service" of ESF components following maintenance activities.
The following administrative controls were reviewed.
Administrative Order No.104, Maintenance Work Request
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(MWR) Procedure, Revision 7, June 11, 1978.
Administrative Order No. 105, Work Permits, Revision 5,
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March 30,1977.
Administrative Order No.113, QuaTity Control Inspection
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Reports and Stop Work Authority, Revision 1, August 5, 1977.
Administrative Order No. 126, Jumper Log, Revision 4
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April 30.1978.
Administrative Order No.127, Modifications to Indian
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Point Facilities, Revision 2, February 5, 1976.
It was noted that all safety-related maintenance is controlled through the use of Work Requests and Work Permits. These control measures specify the return to service of equipment; consequently, individual maintenance tasks were only reviewed on a sampling basis. The following completed Work Requests sere reviewed:
MWR 2040
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MWR 2430
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(4) Review of Plant Surveillane.e Test Procedures The inspector reviewed the following surveillance test procedures to verify that when the surveillance test is completed, the system under test will have been returned to an operable condition.
PT M4, Pressurizer Level, Revision 6
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PT M5, Pressurizer Pressure, Revision 7 PT M8, Steam Generator Level, Revision 7
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PT M9, Containment Pressure, Revision 6.
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PT M14 Safety Injection System Logic Test, Revision
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PT M18, RHR Pumps Functions Test, Revision 8.
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PT M19, Containment Spray Pumps Functional Test, Revision
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PT M21, Diesel Generator Funtional Test, Revision 9.
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PT M23, Motor ABFP, Revision 8.
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PT TM1, Hydrogen Recombiner, Revision 4.
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PT Qll, Determination of SIS Series 856 MOV's Position,
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Revision 1.
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PT M22, Station Battery Surveillance, Revision 9.
PT SA4, Steam Driven Auxiliary Boiler Feed Pump, Revision
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PT SAS, Auxiliary Boiler Feed Pump Disch;rge Valve
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Test, Revision 4.
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PT SA2, Hydorgen Recombiner Control System, Revision 5.
(5) Surveillance Test Results Review The following surveillance test results were reviewed to verify that acceptable criteria were satisfied for the system under test:
PT M4, Pressurizer Level, Revision 6, performed April
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11, 1979.
PT M5, Pressurizer Pressure, Revision 7, performed
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April 6, 1979.
PT M8, Steam Generator Level, Revision 7, performed
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March 17,1979.
PT M9, Containment Pressure, Revision 6, performed
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April 16, 1979.
PT M14B, Safety Injection System Logic Test, Revision
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7, performed April 27, 1979.
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PT M17, Safety Injection Pumps Functional Test, Revision
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11, performed April 26, 1979.
PT M18, RHR Pumps Functional Test, Revision 8, performed
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April 19,1979.
PT M19, Containment Spray Pumps Functional Test, Revision
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7, performed March 29, 1979.
PT M21, Diesel Generator Functional Test, Revision 9,
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performed April 22, 1979.
PT M23, Motor ABFP, Revision 8, perfonned May 4,1979.
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PT TM1, Hydrogen Recombiner, Revision 4, performed
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April 3, 1979.
PT Q11, Determination of SIS Series 856 MOV's Position,
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performed April 25, 1979.
PT M22, Station Battery Surveillance, performed April
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11, 1979.
PT SA4, Steam Driven Auxiliary Boiler Feed Pump, Revision
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5, performed February 7,1979.
PT SAS, Auxiliary Boiler Feed Pump Discharge Valve
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Test, Revision 4, performed February 6, 1979.
PT SA2, Hydrogen Recombiner Control System, Revision 5,
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performed February 8,1979.
(6) Low Pressurizer Level Trips The inspector verified that the pressurizer low level trip bistables were placed in the tripped condition.
These bistables were placed in the tripped condition in accordance with test procedure change 79-11, to E-2, Emergency Core Cooling Actuation, on April 7, 1979.
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(7)
ESF System Operability Following Extended Outages The inspector reviewed COL 46, Plant Startup, Revision 6, March 7, 1979 and Operations Administration Document No. 5, Procedure Adherence and Use, Revision 1, September 15, 1978, and all referuced check off lists (51) to verify that the startup procedure assures the plant is meeting all Technical Specification reqeirements during a plant startup.
(8) Licensee's Utilization of Indeoendent Verifica1. ion The inspector reviewed this area and noted that the licensee utilizes independent verification only in the control of jumpers, and at the conclusion of survei? lance testing, the test engineer records "As-left" valve positions. The watch supervisor then reviews or verifies these valve positions.
(9) [ m gency Boiler Feedwater System Operability The inspector verified by observation that all valves in the emergency boiler feedwater system are in the proper position and that all valves in the system identified by the licensee as requiring locking are actually locked.
b.
Findings Resulting From the Above Review (1) Walk-throughs of the various systems were performed May 7-29, 1979. The inspector performed walk-throughs on all systems previously described in check-off listings, and no valves, switch or power supply was observed to be in a position other than that called for in the COL or as denoted in required changes in system operation. No system was noted to be in a condition that would preclude operation of the system function as intended.
(2) Minor discrepancies were noted in that valve identification tags were missing. The inspector noted that the number of locked valves has been expanded by licensee in order to provide additional control of system status.
These locked valves are in addition to those required to be locked in accordance with the " official" locked valve list.
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The following items were identified to the license for corrective action:
(a) Two valves were not identified in the COL-12 electrical checkout (No. 743 and No. 1870).
(b) Changes to Baron Injection Tank fill system were not reflected in diagrams.
The modification will be included in subsequent drawing change (Sanders Valve).
(c) The BA nitrogen supply tank change was not reflected in COL-12.
(d) Containment pressure sensor 949B was not included in COL-12.
(e) COL-25: A number of missing valve tags"were identified.
(f) The need for calibration of turbine mounted gauges on Auxiliary Steam Boiler Feed Pump was discussed.
The inspector's review with the licensee on the item will be held during subsequent inspection period.
The above items, (a) thru (f), are consit.ed as an unresolved item (247/79-10-01).
5.
Onsite Assessment of Operatino Procedures The inspector verified the following, by direct observation, review oi procedures, and discussions with operators:
(1) No procedures require partial' actuation of Safety Injection to assist in pressurizer level control during routine, operation event induced, pressurizer level trans1ents.
(2) The licensee has discussed with the operators, the conditions identified in the Bulletin 79-06A, item 7.c.
The licensee has not changed his procedures in regard to the securing of the Reactor Coolant Pumps. The licensee has contacted the NSSS and believes that all requireme,ts for RCP operability must be reviewed further prior to complying with the bulletin.
The licensee's response to bulletin will reflect this position.
(3) The reactor operators were reinstructed on tho manner of determining the 50 degree subcooling as required by the bulletin.
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(4) Low water levels in the steam generator is covered by S0P 21.3, Rev. O, Auxiliary Feedwater System, in paragraph 4.2.B.7.
This paragraph addresses the prevention of water hanmer and limits the feed rate to 150 gpm until the generator level is at or above 15%.
No specific mention of feeding a dry generator was noted in the procedure review.
(5) The licensee has no special instructions for placing tags on main control board. The usual means of placing tags was observed by the inspector and does not obscure status indication.
No items of noncompliance were identified.
6.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items; items of noncompliance or deviations. An unresolved item identified during the inspection is discussed in Paragraph 4.b.(2).
Exit Interview At periodic intervals during the course of this inspection, meetings were held with senior facility management to discuss inspection scope and findings.
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