Problems Noted in Control Room Emergency Ventilation SystemsML031250186 |
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: |
08/28/1986 |
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From: |
Jordan E NRC/IE |
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To: |
|
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References |
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IN-86-076, NUDOCS 8608250306 |
Download: ML031250186 (5) |
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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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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>. |
L's 6SSINS No.: 6835 IN 86-76 UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, D.C. 20555 August 28, 1986 IE INFORMATION NOTICE NO. 86-76: PROBLEMS NOTED IN CONTROL ROOM
EMERGENCY VENTILATION SYSTEMS
Addressees
All nuclear power reactor facilities holding an operating license or a con- struction permit.
Purpose
This notice is provided to alert recipients to problems noted in the operation
of control 'room emergency ventilation systems during recent plant visits by an
NRC review team. It is expected that recipients will review this 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 notice do not constitute NRC requirements; therefore, no
specific action or written response is required.
Description of Circumstances
During a recent visit to the Trojan Nuclear Plant, the NRC review team observed
the licensee perform a monthly surveillance test of the cooling capability of
the control room emergency ventilation system. The NRC review team terminated
its involvement shortly after the surveillance test began because the
licensee's procedure was deemed inadequate and the test would not produce any
meaningful results. Specifically, the team noted that the emergency ventila- tion system was initiated with the supply dampers left shut; these dampers were
designed to provide 150 standard cubic feet per minute (cfm) of outside makeup
air in the radiological emergency mode. The toilet and laboratory exhaust fans
(4050 and 3740 cfm capacity, respectively) were left running. This condition
resulted in a slight vacuum in the control room, although the system is
designed to maintain 1/8-inch H20 positive pressure in the emergency mode. In
addition, the humidity control had been adjusted to 100 percent (thus the
heaters would remain off for any humidity less than 100 percent) even though
the Technical Specifications require the system to be tested with the heaters
on.
When the makeup air dampers were opened, it was determined that 460 cfm of
filtered outside air was being supplied instead of the designed 150 cfm. *In
addition, it was discovered that a 2-inch drain pipe on the cooling units down
stream of the filter housing was drawing 41 cfm of unfiltered outside air into
the system. The drain pipe was connected by a drain line header to both trains
8608250306
IN 86-76 August 28, 1986 of the emergency ventilation systems. This drain arrangement constituted
common-mode failure and a lack of train separation of an engineered safety a
feature. On the basis of these findings, Region V inspectors asked Trojan
recalculate the operator doses expected during an accident. The licensee to
calculated 1.7 rem whole body, 195 rem to the thyroid, and 30.6 rem to the
skin. The general design criteria (GDC 19) in Appendix A of 10 CFR Part
specifies that the control room be designed to allow occupancy through the50
course of an accident without exceeding 5 rem whole body or its equivalent
any part of the body. Because 30 rem to any organ (skin or thyroid) is to
equiva- lent to a 5 rem whole-body dose, a violation resulted. The violation was
categorized as a Severity Level II violation because both trains of the
were inoperable for a long period of time and a civil penalty resulted. system
The NRC has made several plant visits to review control room ventilation
systems as part of the resolution of the generic issue on control room habit- ability (Item III D.3.4 of NUREG-0737). Although Trojan has been the only
plant visit to date with problems severe enough to result in an enforcement
action, several similar problems have been noted at other facilities visited.
Attachment 1 provides a discussion of these common problems noted. Currently
the NRC is scheduled to visit six more facilities in response to the generic
issue.
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.
Edwarcvi Jordan, Director
Divis ph of Emergency Preparedness
and Engineering Response
Office of Inspection and Enforcement
Technical Contacts: Roger L. Pedersen, IE
(301)492-9061 John J. Hayes, NRR
(301)492-7471 Attachments:
1. Summary of Control Room Habitability Reviews
2. List of Recently Issued IE Information Notices
Attachment 1 IN 86-76 August 28, 1986 SUMMARY OF CONTROL ROOM HABITABILITY REVIEWS
The following is a summary of the common problems noted in control room emer- gency ventilation systems during recent NRC plant visits to gather information
on Control Room Habitability (Generic Issue 83). Items discussed were noted at
two or more facilities visited.
System Understanding- The NRC review team noted that there appeared to be no individual or group
designated as responsible for the ventilation systems at the plant visited.
This appears to lead to a lack of understanding of the systems and their
operation. Most of the systems reviewed to date do not accurately reflect the
system descriptions provided by the licensees in their submittals required by
item III 0.3.4 of TMI Action Plan (NUREG-0737). In addition, the following
concerns were noted in the way surveillance testing is being performed on these
systems.
1. Most plants measured control room temperature in the center of the room.
However, the basis of the requirement is to ensure operability of
solid-state electrical equipment, not operator comfort. Therefore, measuring the air temperature at the instrument panels is more appropriate
(see IE IN 85-89 for additional information on the effects of control room
cooling on solid-state instrumentation).
2. The purpose of maintaining a positive pressure in the control room during
emergency operation is to ensure any leakage is out of (rather than into)
the control room. Several licensees show compliance with their technical
specifications by comparing control room pressure to the outside atmo- spheric pressure. Because areas adjacent to the control room envelope
(CRE) can be at higher-than-atmospheric pressure, a relative negative
control room pressure may exist across the CRE boundary, providing a
motive force for inleakage. This is also a concern where the control room
ventilation system is routed through adjacent areas. Clearly it is
appropriate to measure the differential pressure relative to the highest
pressure adjacent to the CRE boundary or ventilation system.
3. Laboratory testing of charcoal efficiency is being performed at tempera- tures much higher than any temperature expected during the course of an
accident. This can result in an erroneously high efficiency measurements.
Retention efficiencies as low as 70% were noted when samples of charcoal
that had just passed its surveillance tests (greater than 90% efficient)
were retested at 30'C.
Attachment 1 IN 86-76 August 28, 1986 Excessive Unfiltered Inleakage
poor.
The general condition of some of the ventilation systems reviewed was of
Many of the following conditions were discovered that resulted in leakage
unfiltered air into the systems reviewed.
1. Holes and openings: Many holes left from construction and unplugged units
openings were found in the system duct work and in the air handling
themselves.
2. Drains: Uncapped drains (or drains improperly left open to the atmosphere)
system.
were found that allow the air handling units to draw air into the
In addition, water loop seals in some drains were found dry.
unsealed
3. CRE penetrations: Some control rooms were found with "numerous"
penetrations across the CRE.
team performed
Many of these problems were not discovered until the NRC review room venti- flow balance and differential pressure measurements on the control
lation systems.
I Attachment 2 IN 86-76 August 28, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
Information Date of
Notice No. Subject Issue Issued to
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 RHR Valves
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
Embrittlement
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 BWR facilities
Caused By The Panalarm Model holding an OL or CP
86 Thermocouple Monitor
86-69 Scram Solenoid Pilot Valve 8/18/86 All BWR facilities
(SSPV) Rebuild Kit Problems holding an OL or CP
86-68 Stuck Control Rod 8/15/86 All BWR facilities
holding an OL or CP
86-67 Portable Moisture/Density 8/15/86 All NRC licensees
Gauges: Recent Incidents And authorized to possess, Common Violations Of Require- use, transport, and
ments For Use, Transportation, store sealed sources
And Storage x
86-66 Potential For Failure Of 8/15/86 All power reactor
Replacement AC Coils Supplied facilities holding
By The Westinghouse Electric an OL or CP
Corporation For Use In Class
1E Motor Starters And
Contractors
OL = Operating License
CP = Construction Permit
|
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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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