Unit Startup with Degraded High Pressure Safety Injection SystemML031250214 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Issue date: |
09/12/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-080, NUDOCS 8609100228 |
Download: ML031250214 (4) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Skagit, Marble Hill |
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Category:NRC Information Notice
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Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>. |
,6 G NAL SSINS No.:
IN 86-80
6835 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 September 12, 1986 IE INFORMATION NOTICE NO. 86-80: UNIT STARTUP WITH DEGRADED HIGH
PRESSURE SAFETY INJECTION SYSTEM
Addressees
All nuclear power reactor facilities holding an operating license or a
construction permit.
Purpose
The purpose of this notice is to inform recipients of an event where unit
startup involved improper interpretation of the terms "OPERABLE" and
"OPERABILITY" in the technical specifications. It is expected that recipients
will review the information for applicability to their facilities and consider
actions, if appropriate, to preclude a similar problem occurring at their
facilities. However, suggestions contained in this information notice do not
constitute NRC requirements; therefore, no specific action or written response
is required.
Description of Circumstances
At the McGuire Station on November 2, 1985, a single failure in a shared
instrument air system caused a trip of both units from 100% power and a safety
injection in Unit-1. A detailed sequence of events is provided for information
in attachment 1. The isolation valves between the volume control tank (VCT)
and the charging pumps closed as designed when the SI signal initiated a trans- fer of the charging pump suction to the refueling water storage tank from the
VCT. Later, when the SI was reset, it was discovered that the VCT isolation
valve motor operators had burned-up due to overload.
Although work requests were written to repair both of the valves, operations
personnel made the erroneous decision to start-up based on the determination
that these VCT isolation valves are not in the direct ECCS flow path required
by technical specifications. They believed that the HPSI system was still
capable of performing its design requirement. The unit entered the start-up
mode (mode 2) at about 6:15 a.m. the following day, (November 3, 1985), but
only stayed in this mode until 12:55 p.m. when mode 3 was re-entered to repair
a severed instrument fitting on the secondary side of a steam generator.
Discussion:
The safety significance of this event is that the VCT isolation valves would
not have automatically closed if an SI signal were received. The charging pumps
8609100228
u 4
? . _
IN 86-80
September 12, 1986 would then be taking suction from both the VCT and the RWST with the following
possible consequences: (1) the VCT could be drained allowing hydrogen gas to
be entrained in the charging pump suction, possibly leading to gas binding of
the charging pumps and (2) the water injected into the reactor vessel would
have a lower boron concentration than it would in the required line-up.
Duke Power personnel made their decision to start-up the unit on the basis that
neither of the two valves in question is specifically identified in Technical
Specification 3.5.2 as being a part of the required ECCS flow path. The tech- nical specification requires "an OPERABLE flow path capable of taking suction
from the RWST on an SI signal and automatically transferring suction to the
containment sump during the recirculation phase of operation." However, the
standard definition of OPERABLE requires that all necessary attendant instru- mentation, controls, normal and emergency power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, sub- system, train, component or device to perform its function(s) are also capable
of performing their related support function(s). A generic letter was issued by
the NRC Office of Nuclear Reactor Regulation on April 10, 1980 to clarify the
meaning of the term OPERABLE and to request licensees to take specific actions
to assure that the term is appropriately applied at their facilities. This
definition of operability was also part of the McGuire technical specifications
at the time of the event.
IE Information Notice (IN) 86-38, entitled "Deficient Operator Actions Following
Dual Function Valve Failures" also addresses operator actions with regard to
valves that serve more than one function. The valves addressed in IN 86-38 not
only accommodate emergency core cooling flow, but also provide a containment
isolation function. The information notice also refers to the generic letter
dated April 10, 1980 that requests licensees to adopt the standard definition of
OPERABLE in their technical specifications.
No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the Regional
Administrator of the appropriate regional office or this office.
war/. k*df rect or
Division Emergency Preparedness
and Eng neering Response
Office of Inspection and Enforcement
Technical Contacts: Joe Giitter, IE
(301) 492-9001 William T. Orders, RII
(704) 875-1681 Attachments:
1. Detailed Sequence of Events
2. List of Recently Issued IE Information Notices
Attachment 1 IN 86-80
September 12, 1986 11/2/85 A fatigue-induced failure of the discharge line from one of three
'0640 instrument air compressors, which comprise a shared instrument air
system, resulted in the loss of instrument air pressure to all loads
on both units. The main feedwater flow control valves on both units
closed as designed as a result of the loss of instrument air. Due to
low-low steam generator levels, both units tripped from 100% power.
The auxiliary feedwater systems auto-started and provided feedwater
to the team generators.
A safety injection (SI) signal was received on Unit 1 when the reactor
coolant system pressure dropped below the SI set point of 1845 psig.
Injection occurred for about 10 minutes. The pressure decrease was
caused by several factors: (1) post-trip steam loads were higher
than normal because the main steam drains opened on loss of instru- ment air; (2) three steam generator power operated relief valves and
code safeties opened to relieve the initial pressure transient; (3)
pressurizer heaters failed to energize as required; and (4) steam
generators were overfed because flow control valves in the auxiliary
feedwater system went open as a result of the loss of instrument air;
and (5) Unit 1 was providing house load auxiliary steam.
When the SI signal was received, the high-pressure safety injection
(HPSI) charging pump suction transferred from the volume control tank
(VCT) to the refueling water storage tank (RWST) as designed. This
requires that the valves between the RWST and the charging pumps open
and the two motor operated isolation valves between the VCT and the
charging pumps closed. The isolation valves between the VCT and the
charging pumps closed (i.e., the required safe position).
SI was reset, the isolation valves could not be opened from the
control room. An equipment operator was dispatched to manually open
the valves. The valves were subsequently determined to be electri- cally inoperable because the valve motors had burned-up due to over- load. Work requests were written to repair both of the valves.
Operations personnel made the erroneous decision to start-up based
on the determination that these VCT isolation valves are not in the
direct ECCS flow path required by technical specifications. They
believed that the HPSI system was still capable of performing its
design requirement.
11/3/85 Unit entered the start-up mode (mode 2) with the VCT isolation valves
-0615 open and electrically inoperable. The unit did not exceed 2% reactor
power while in mode 2.
11/3/85 Mode 3 was re-entered to repair a severed instrument fitting on the
-1255 secondary side of a steam generator.
IN 86-80
September 12. 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
86-79 Degradation Or Loss Of 9/2/86 All power reactor
Charging Systems At PYR facilities holding
Nuclear Power Plants Using an OL or CP
Swing-Pump Designs
86-78 Scram Solenoid Pilot Valve 9/2/86 All BWRfacilities
(SSPV) Rebuild Kit Problems holding an OL or CP
86-77 Computer Program Error Report 8/28/86 All power reactor
Handling facilities holding
an OL or CP and
nuclear fuel man- ufacturing facilities
86-76 Problems Noted In Control 8/28/86 All power reactor
Room Emergency Ventilation facilities holding
Systems an OL or CP
86-75 Incorrect Maintenance 8/21/86 All power reactor
Procedure On Traversing facilities holding
Incore Probe Lines an OL or CP
86-74 Reduction Of Reactor Coolant 8/20/86 All BWR facilities
Inventory Because Of Misalign- holding an OL or CP
ment Of RHRValves
86-73 Recent Emergency Diesel 8/20/86 All power reactor
Generator Problems facilities holding
an OL or CP
86-72 Failure 17-7 PH Stainless 8/19/86 All power reactor
Steel Springs In Valcor facilities holding
Valves Due to Hydrogen an OL or CP
Embritt lement
86-71 Recent Identified Problems 8/19/86 All power reactor
With Limitorque Motor facilities holding
Operators an OL or CP
86-70 Spurious System Isolation 8/18/86 All GE 8WRfacilities
Caused By The Panalarm Model holding an OL or CP
86 Thermocouple Monitor
OL = Operating License
CP = Construction Permit
UNITED STATES
NUCLEAR REGULATORY COMMISSION FIRST CLASS MAIL
WASHINGTON. D.C. 20565 POSTAGE & FEES PAIO
USN RC
OSFICIALt BUSINESS WASH 0 C
PEMAITV fOX PRIVATE USE 30 PERMIT No GL67 U
II
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list | - Information Notice 1986-01, Failure of Main Feedwater Check Valves Causes Loss of Feedwater System Integrity and Water-Hammer Damage (6 January 1986)
- Information Notice 1986-02, Failure of Valve Operator Motor During Environmental Qualification Testing (6 January 1986)
- Information Notice 1986-03, Potential Deficiencies in Enviromental Qualification of Limitorque Motor Valve Operator Wiring (14 January 1986)
- Information Notice 1986-04, Transient Due to Loss of Power to Intergrated Control System at a Pressurized Water Reactor Designed by Babcock & Wilcox (31 January 1986)
- Information Notice 1986-05, Main Steam Safety Valve Test Failures and Ring Setting Adjustments (31 January 1986)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, While Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986, Topic: Control of Heavy Loads)
- Information Notice 1986-06, Failure of Lifting Rig Attachment, while Lifting Upper Guide Structure at St. Lucie Unit 1 (3 February 1986)
- Information Notice 1986-07, Lack of Detailed Instruction & Inadequate Observance of Precautions During Maintenance & Testing of Diesel Generator Woodward Governors (3 February 1986)
- Information Notice 1986-08, Licensee Event Report (LER) Format Modification (3 February 1986)
- Information Notice 1986-09, Failure of Check & Stop Check Valves Subjected to Low Flow Conditions (3 February 1986)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting From Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-10, Feedwater Line Break (10 November 1988, Topic: Coatings, Anchor Darling)
- Information Notice 1986-10, Degradation of Reactor Coolant System Pressure Boundary Resulting from Boric Acid Corrosion. (5 January 1995, Topic: Boric Acid, Stress corrosion cracking)
- Information Notice 1986-11, Anomalous Behavior of Recirculation Loop Flow in Jet Pump BWR Plants (31 December 1986)
- Information Notice 1986-13, Standby Liquid Control System Squib Valves Failure to Fire (21 February 1986, Topic: Squib)
- Information Notice 1986-13, Standby Liquid Control Squib Valves Failure to Fire (5 August 1986, Topic: Squib)
- Information Notice 1986-14, Overspeed Trips of AFW, HPCI & RCIC Turbines (26 August 1991, Topic: Fire Barrier)
- Information Notice 1986-14, Overspeed Trips of Afw, HPCI & RCIC Turbines (26 August 1991)
- Information Notice 1986-15, Loss of Offsite Power Caused by Problems in Fiber Optics Systems (10 March 1986, Topic: Squib)
- Information Notice 1986-16, Failures to Identify Containment Leakage Due to Inadequate Local Testing of BWR Vacuum Relief System Valves (11 March 1986, Topic: Squib)
- Information Notice 1986-17, Update of Failure of Automatic Sprinkler System Valves to Operate (24 March 1986, Topic: Squib)
- Information Notice 1986-18, NRC On-Scene Response During a Major Emergency (26 March 1986, Topic: Squib, Backfit)
- Information Notice 1986-19, Reactor Coolant Pump Shaft Failure at Crystal River (21 March 1986, Topic: Squib)
- Information Notice 1986-20, Low-Level Radioactive Waste Scaling Factors, 10 CFR Part 61 (28 March 1986, Topic: Squib)
- Information Notice 1986-21, Recognition of American Society of Mechanical Engineers Accreditation Program for N Stamp Holders (31 March 1986, Topic: Squib)
- Information Notice 1986-22, Underresponse of Radiation Survey Instrument to High Radiation Fields (31 March 1986, Topic: High Radiation Area, Squib)
- Information Notice 1986-23, Excessive Skin Exposures Due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-23, Excessive Skin Exposures due to Contamination with Hot Particles (9 April 1986)
- Information Notice 1986-24, Respirator Users Notice: Increased Inspection Frequency for Certain Self-Contained Breathing Apparatus Air Cylinders (11 April 1986, Topic: Hydrostatic)
- Information Notice 1986-25, Traceability and Material Control of Material and Equipment, Particularly Fasteners (11 April 1986)
- Information Notice 1986-26, Potential Problems in Generators Manufactured by Electrical Products Incorporated (17 April 1986)
- Information Notice 1986-27, Access Control at Nuclear Facilities (21 April 1986, Topic: Contraband)
- Information Notice 1986-28, Telephone Numbers to the NRC Operations Center and Regional Offices (24 April 1986)
- Information Notice 1986-29, Effects of Changing Valve Moter-Operator Switch Settings (25 April 1986)
- Information Notice 1986-30, Design Limitations of Gaseous Effluent Monitoring Systems (29 April 1986)
- Information Notice 1986-31, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges (14 July 1986)
- Information Notice 1986-32, Request for Collection of Licensee Radioactivity Measurements Attributed to Chernobyl Nuclear Plant Accident (2 May 1986, Topic: Chernobyl)
- Information Notice 1986-33, Information for Licensee Regarding the Chernobyl Nuclear Plant Accident (6 May 1986, Topic: Chernobyl)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & Their Actuators (13 May 1986)
- Information Notice 1986-34, Improper Assembly, Material Selection, & Test of Valves & their Actuators (13 May 1986)
- Information Notice 1986-35, Fire in Compressible Material at Dresden Unit 3 (15 May 1986, Topic: Chernobyl)
- Information Notice 1986-36, Change in NRC Practice Regarding Issuance of Confirming Letters to Principal Contractors (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-37, Degradation of Station Batteries (16 May 1986, Topic: Chernobyl)
- Information Notice 1986-38, Deficient Operator Actions Following Dual Function Valve Failures (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-39, Failures of RHR Pump Motors and Pump Internals (20 May 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in Bwrs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-40, Degraded Ability to Isolate the Reactor Coolant System from Low-Pressure Coolant Systems in BWRs (5 June 1986, Topic: Chernobyl)
- Information Notice 1986-41, Evaluation of Questionable Exposure Readings of Licensee Personnel Dosimeters (9 June 1986, Topic: Chernobyl)
- Information Notice 1986-42, Improper Maintenance of Radiation Monitoring Systems (9 June 1986, Topic: Temporary Modification, Chernobyl)
- Information Notice 1986-43, Problems with Silver Zeolite Sampling of Airborne Radioiodine (10 June 1986, Topic: Chernobyl)
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