Recent Discovery of a Phenomenon Not Previously Considered in Design of Secondary Containment Pressure Control ML031150101 Person / Time 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 , 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 , Crane Issue date:
09/19/1988 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-88-076 , NUDOCS 8809130350Download: ML031150101 (8)
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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 ,
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 ,
Crane Category:NRC Information Notice
[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 [[: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 [[:Crane]] </code>.
Contents
1 NUCLEAR REGULATORY COMMISSION 2 September 19, 1988 3 PREVIOUSLY CONSIDERED IN THE DESIGN OF 4 Addressees 5 Purpose 6 Description of Circumstances
6.1 Under these circumstances, the 6.2 After completion of this modification 6.3 Division of Operational Events Assessment 6.4 Technical Contact: 6.5 Jack Kudrick, NRR 6.6 Effect of Outside Temperature on Reactor 6.7 Attachment 1 6.8 September 19, 1988 TABLE 1 6.9 OUTSIDE TEMPERATURE 6.10 Attachment 2 6.11 September 19, 1988 LIST OF RECENTLY ISSUED 6.12 Disabling of Diesel 6.13 Potentially Inadequate 6.14 PWRs During Recirculation 6.15 Characteristics of 6.16 Inadequacies in the Design 6.17 Possible Environmental 6.18 Request for Collection 6.19 Measurements Attributed 6.20 Check Valve Inservice 6.21 Deficiencies 6.22 Binding in HFA Relays 6.23 All holders of OLs 6.24 All holders of OLs 6.25 All holders of OLs 6.26 All holders of OLs 6.27 All holders of OLs 6.28 All holders of OLs 6.29 All holders of OLs 6.30 Supplement 1 6.31 Refurbished Valves 6.32 All holders of OLs 6.33 Filled Loop Seals Using 6.34 All holders of OLs 6.35 Charles E. Rossi, Director 6.36 Office of Nuclear Reactor Regulation 6.37 Technical Contact: 6.38 Jack Kudrick, NRR 6.39 Building Delta 6.40 Temperature on Reactor 6.41 Charles E. Rossi, Director 6.42 Office of Nuclear Reactor Regulation 6.43 Technical Contact: 6.44 Jack Kudrick, NRR 6.45 Building Delta 6.46 Temperature on Reactor 6.47 Charles E. Rossi, Director 6.48 Office of Nuclear Reactor Regulation 6.49 Technical Contact: 6.50 Building Delta 6.51 Kudrick, NRR 6.52 Issued NRC Information Notices 6.53 BMann 75 i44
NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON , D.C.
20555
September 19, 1988 NRC INFORMATION NOTICE NO. 88-76: RECENT DISCOVERY OF A PHENOMENON NOT
PREVIOUSLY CONSIDERED IN THE DESIGN OF SECONDARY CONTAINMENT PRESSURE CONTROL
Addressees All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose This information notice is being provided to alert addressees to a recent
discovery of a phenomenon not previously considered in the design of the
secondary containment pressure control system, which could cause the secondary
containment pressure to rise above allowable values. It is expected that reci- pients will review the information for applicability to their facilities and
consider actions, as appropriate, to avoid similar problems. However, sugges- tions contained in this information notice do not constitute NRC requirements;
therefore, no specific action or written response is required.
Description of Circumstances In Licensee Event Report (LER) 87-065-00, dated November 10, 1987, Niagara
Mohawk Power Corporation, licensee for Nine Mile Point, Unit 2 (NMP 2), noti- fied the NRC that the NMP 2 secondary containment had not been maintained at
the required subatmospheric pressure at higher building elevations because
of a phenomenon not considered in the design of the secondary containment
pressure control system.
At NMP 2, the instruments that measure the differential pressure (delta P)
between the interior of the secondary containment and the atmosphere sense
pressure at an elevation of approximately 265 feet (near the bottom of the
building).
The delta P at the upper portion of the building (at an elevation
of 435 feet) is obtained by taking into account the interior and exterior
static pressure gradients between the elevations. The design of the system
did not take into account the temperature-induced difference in the pressure
gradients inside and outside the secondary containment . Whenever the outside
temperature is lower than the temperature maintained in the secondary contain- ment, the vertical pressure decrease at the higher elevation outside the
secondary containment is greater than the pressure decrease inside the secon- dary containment because of the higher density of the colder air.
rem
1
350 7
s-/
IN 88-76 September 19, 1988 The calculated values for reactor building delta P as a function of outside air
temperature at an elevation of 435 feet demonstrate this effect (Table 1).
For
outside temperatures lower than reactor building temperatures, pressure differ- entials between the inside and outside of the building at upper elevations were
calculated to be less negative than the allowable value of -0.25 inch water
gauge (WG).
The installed instrumentation was insufficient to accurately
determine reactor building differential pressure at higher elevations.
Discussion:
In a postulated accident, the secondary containment structure, which is nor- mally maintained at a pressure lower than atmospheric, and supporting systems
would collect and process radioactive material that may leak from the primary
containment. Whenever an outward positive pressure exists across the secondary
containment boundary, the leakage prevention function of the secondary contain- ment is assumed to be negated and all primary containment leakage is assumed to
be released directly into the environment.
Under these circumstances, the offsite dose limits stated in 10 CFR Part 100 for fission product releases
from postulated accidents could be exceeded.
As stated in Branch Technical Position (BTP ) CSB 6-3 (NUREG-0800 ), a "positive"
pressure in this regard is defined as any pressure greater than -0.25 inch WG,
to conservatively account for wind loads and the uncertainty in pressure meas- urements. In addition to these factors, the problems at NMP 2 show that the
effect of delta P gradients caused by low outside air temperatures can be an
important factor in the design of the secondary containment pressure control.
Because its density is higher, cold air exerts more force per increment of
elevation than warm air.
Thus, while maintaining the -0.25 inch WG differ- ential pressure in lower portions of the secondary containment , the delta P
decreases at higher elevations and becomes ."positive" as demonstrated in
Table 1. It should also be noted that this effect increases as humidity
increases in the reactor building.
Subsequent to discovery of this phenomenon, the licensee took several cor- rective actions.
The setpoint on the delta P pressure transmitters was reset
from 0.33 inch to 0.76 inch vacuum WG.
The licensee's analysis indicated that
this would assure a delta P of at least 0.25 inch vacuum WG at upper elevations
for a temperature differential of 850F between reactor building interior and
exterior. A modification was also initiated to relocate the delta P elements
to the roof of the reactor building.
After completion of this modification the delta P setpoint would be reset to the original value of 0.33 inch vacuum
WG. With implementation of this modification, a minimum delta P of 0.25 inch
vacuum WG would be established in the reactor building. A considerably larger
delta P in the lower elevations of the reactor building would occur on days
with low outside temperature.
IN 88-76 September 19, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charl es .:ogsi, D ~rector
Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Technical Contact: Jack Kudrick, NRR (301) 492-0871 Attachments:
1. Table 1 -
Effect of Outside Temperature on Reactor Building Delta P
2. List of Recently Issued NRC Information Notices
Attachment 1 IN 88-76
September 19, 1988 TABLE 1 EFFECT OF OUTSIDE TEMPERATURE ON REACTOR BUILDING DELTA P
OUTSIDE TEMPERATURE (OF)
REACTOR BUILDING DELTA P*
(inches water gauge [WG])
85
60
40
20
0
-20
-0.25
-0.17
-0.10
-0.03
+0.06
+0.15
Reactor building delta P at elevation 435 feet with -0.25 inch (water gauge ) measured at elevation 265 feet; building temperature at 850F, 0% humidity.
Attachment 2 IN 88-76
September 19, 1988 LIST OF RECENTLY ISSUED NRC INFORMATION NOTICES
Information
Date of
Notice No.
Subject
Issuance
Issued to
88-75
88-74
88-73
88-72
88-71
88-70
88-69
Disabling of Diesel Generator Output Circuit
Breakers by Anti-Pump
Circuitry
Potentially Inadequate Performance of ECCS In
PWRs During Recirculation Operation Following a LOCA
Direction-Dependent Leak
Characteristics of Containment Purge Valves
Inadequacies in the Design of dc Motor-Operated Valves
Possible Environmental Effect of the Reentry
of COSMOS 1900 and
Request for Collection of Licensee Radioactivity
Measurements Attributed to That Event
Check Valve Inservice Testing Program
Deficiencies Movable Contact Finger
Binding in HFA Relays Manufactured by General
Electric (GE )
9/16/88
9/14/88
9/8/88
9/2/88
9/1/88
8/29/88
8/19/88
All holders of OLs or CPs for nuclear
power reactors.
All holders of OLs or CPs for W and
B&W-designed nuclear
power reactors.
All holders of OLs or CPs for nuclear
power reactors.
All holders of OLs or CPs for nuclear
power reactors.
All holders of OLs or CPs for nuclear
power reactors, fuel
cycle licensees, and Priority 1 material licensees.
All holders of OLs or CPs for nuclear
power reactors.
All holders of OLs or CPs for nuclear
power reactors.
88-48,
Supplement 1 Licensee Report of Defective
Refurbished Valves 8/24/88
All holders of OLs or CPs for nuclear
power reactors.
88-68 Setpoint Testing of Pres- surizer Safety Valves with
Hydraulic Assist Devices
8/22/88
All holders of OLs or CPs for nuclear
power reactors.
OL = Operating License
CP = Construction Permit
IN 88-76 September 19, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contact: Jack Kudrick, NRR (301) 492-0871 Attachments:
1. Table 1 - Effect
Building Delta 2. List of Recently
of Outside
P
Issued NRC
Temperature on Reactor Information Notices
SEE PREVIOUS CONCURRENCES C/OGCB:DOEA:NRR
LCEfXrr-'-"1 CHBerlinger
09Ka 88
\\9/07/88
C/PSB:DEST:NRR*'SAD/DEST:NRR JCraig
AThadani
07/07/88
07/08/88
TechEd
07/13/88
LShao
07/11/88
BMann
07/06/88
JKudrick
07/07/88
IN 88-XX
September xx, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contact: Jack Kudrick, NRR (301) 492-0871 Attachments:
1. Table 1 - Effect
Building Delta 2. List of Recently
of Outside
P
Issued NRC
Temperature on Reactor Information Notices
SEE PREVIOUS CONCURRENCES OGCB:DOEA:NRR *PSB:DEST:NRR BMann
JKudrick
07/06/88
07/07/88 D/DOEA:NRR
C/ B:DOEA:NRR
CERossi
CHBerlinger
TechEd
09/ /88
09/07/88
07/13/88
C/PSB:DEST:NRR*SAD/DEST:NRR JCraig
AThadani
LShao
07/07/88
07/08/88
07/11/88
IN 88-XX
July xx, 1988 No specific action or written response is required by this information notice.
If you have any questions about this matter, please contact the technical
contact listed below or the Regional Administrator of the appropriate NRC
regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contact: ,
Attachments:
1. Table 1 - Effect
Building Delta 2. List of Recently
Jack
(301)
Kudrick, NRR 492-0871 of Temperature on Reactor
P
Issued NRC Information Notices OGCB:DQEA:NRR
BMann 75 i44 07/6 /88 D/DOEA:NRR
CERossi
PS b
NRR
/
NRR JKudn k
JTN
07/1
8
8
/88 C/OGCB:DOEA:NRR
CHBerlinger
07/ /88 SAD/DEST:N
ATh34ani I'
07/K /88 RPB:ARM
TechEd
07//3/8,N
D/DES~kNK
07t/88
list Information Notice 1988-01, Safety Injection Pipe Failure 27 January 1988 Topic Unidentified leak Water hammer Information Notice 1988-03, Cracks in Shroud Support Access Hole Cover Welds 2 February 1988 Topic Intergranular Stress Corrosion Cracking Stolen Information Notice 1988-04, Inadequate Qualification and Documentation of Fire Barrier Penetration Seals 5 February 1988 Topic Fire Barrier Fire Watch Stolen Information Notice 1988-05, Fire in Annunciator Control Cabinets 12 February 1988 Topic Stolen Information Notice 1988-06, Foreign Objects in Steam Generators 29 February 1988 Topic Eddy Current Testing Stolen Information Notice 1988-07, Inadvertent Transfer of Licensed Material to Uncontrolled Locations 7 March 1988 Topic Stolen Overexposure Information Notice 1988-08, Chemical Reactions with Radioactive Waste Solification Agents 14 March 1988 Topic Process Control Program Stolen Information Notice 1988-09, Reduced Reliability of Steam-Driven Auxiliary Feedwater Pumps Caused by Instability of Woodward PG-PL Type Governors 18 March 1988 Topic Overspeed trip Overspeed Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 FR 43950, October 31, 1988) 23 December 1988 Topic Fatality Overexposure Information Notice 1988-10, Memo of Understanding Between NRC and OSHA Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988) 23 December 1988 Topic Fatality Overexposure Information Notice 1988-10, Memorandum of Understanding Between NRC and Osha Relating to NRC-Licensed Facilities (53 Fr 43950, October 31, 1988. 23 December 1988 Topic Fatality Overexposure Information Notice 1988-11, Potential Loss of Motor Control Center And/Or Switchboard Function Due to Faulty Tie Bolts 7 April 1988 Information Notice 1988-12, Overgreasing of Electric Motor Bearings 12 April 1988 Topic Hardened grease Information Notice 1988-13, Water Hammer & Possible Piping Damage Caused by Misapplication of Kerotest Packless Metal Diaphragm Globe Valves 18 April 1988 Topic Water hammer Information Notice 1988-14, Potential Problems with Electrical Relays 18 April 1988 Information Notice 1988-15, Availability of Us Food & Drug Administration (FDA) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine 18 April 1988 Topic Water hammer Potassium iodide Information Notice 1988-15, Availability of Us Food & Drug Administration (Fda) Approved Potassium Iodide for Use in Emergencies Involving Radioactive Iodine 18 April 1988 Topic Potassium iodide Information Notice 1988-16, Identify Waste Generators in Shipments of Low-Level Waste to Land Disposal Facilities 22 April 1988 Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants 22 April 1988 Topic Safe Shutdown Weld Overlay Feedwater Heater Through-Wall Leak Water hammer Information Notice 1988-18, Malfunction of Lockbox on Radiography Device 25 April 1988 Topic Overexposure Information Notice 1988-19, Questionable Certification of Class Ie Components 26 April 1988 Topic Water hammer Information Notice 1988-19, Questionable Certification of Class IE Components 26 April 1988 Information Notice 1988-20, Unauthorized Individuals Manipulating Controls and Performing Control Room Activities 5 May 1988 Information Notice 1988-21, Inadvertent Criticality Events at Oskarshamn and at U.S. Nuclear Power Plants 9 May 1988 Topic Shutdown Margin Information Notice 1988-22, Disposal of Sludge from Onsite Sewage Treatment Facilities at Nuclear Power Stations 12 May 1988 Topic Sewage Treatment Plant Information Notice 1988-23, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-Of-Coolant Accident 12 May 1988 Information Notice 1988-24, Failures of Air-Operated Valves Affecting Safety-Related Systems 13 May 1988 Information Notice 1988-25, Minimum Edge Distance for Expansion Anchor Bolts 16 May 1988 Topic Earthquake Information Notice 1988-26, Falsified Pre-Employment Screening Records 16 May 1988 Information Notice 1988-27, Deficient Electrical Terminations Identified in Safety-Related Components 18 May 1988 Information Notice 1988-28, Potential for Loss of Post-Loca Recirculation Capability Due to Insulation Debris Blockage 19 May 1988 Topic Coatings Information Notice 1988-29, Deficiencies in Primary Containment Low-Voltage Electrical Penetration Assemblies 24 May 1988 Information Notice 1988-30, Target Rock Two-State SRV Setpoint Drift Update 25 May 1988 Information Notice 1988-31, Steam Generator Tube Rupture Analysis Deficiency 25 May 1988 Topic Loss of Offsite Power Information Notice 1988-32, Prompt Reporting to NRC of Significant Incidents Involving Radioactive Material 25 May 1988 Topic Overexposure Information Notice 1988-33, Recent Problems Involving the Model Spec 2-T Radiographic Exposure Device 27 May 1988 Topic Depleted uranium Information Notice 1988-34, Nuclear Material Control & Accountability of Non-Fuel Special Nuclear Material at Power Reactors 31 May 1988 Information Notice 1988-36, Possible Sudden Loss of RCS Inventory During Low Coolant Level Operation 8 June 1988 Information Notice 1988-37, Flow Blockage of Cooling Water to Safety System Components 14 June 1988 Topic Ultimate heat sink Information Notice 1988-38, Failure of Undervoltage Trip Attachment of General Electric Circuit Breakers 15 June 1988 Information Notice 1988-39, Loss of Recirculation Pumps with Power Oscillation Event 15 June 1988 Topic Feedwater Heater Information Notice 1988-40, Examiners Handbook for Developing Operator Licensing Examinations 22 June 1988 Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (RERs) 22 June 1988 Information Notice 1988-41, Physical Protection Weaknesses Identified Through Regulatory Effectiveness Reviews (Rers) 22 June 1988 Information Notice 1988-42, Circuit Breaker Failures Due to Loose Charging Spring Motor Mounting Bolts 23 June 1988 Topic Locktite Information Notice 1988-43, Solenoid Valve Problems 23 June 1988 Topic Stroke time Information Notice 1988-44, Mechanical Binding of Spring Release Device in Westinghouse Type DS-416 Circuit Breakers 24 June 1988 Information Notice 1988-45, Problems in Protective Relay & Circuit Breaker Coordination 7 July 1988 Topic Safe Shutdown Information Notice 1988-46, Licensee Report of Defective Refurbished Circuit Breakers 8 July 1988 Information Notice 1988-47, Slower-than-Expected Rod-drop Times 14 July 1988 ... further results