Plant Operation Beyond Analyzed Conditions ML031130392 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:
12/23/1987 From:
Rossi C Office of Nuclear Reactor Regulation To:
References IN-87-065 , NUDOCS 8712170119Download: ML031130392 (7)
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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>.
IN 87-65
Contents
1 UNITED STATES 2 OFFICE OF NUCLEAR REACTOR REGULATION 3 December 23, 1987 4 Addressees 5 Purpose 6 Description of Circumstances
6.1 The analysis of containment performance following a 6.2 Under these circumstances, equipment that is 6.3 Since the plant has been operating 6.4 December 23, 1987 6.5 INFORWATION NOTICES 1387 6.6 Conviction for Falsatication 6.7 Initiation From the Control 6.8 Inadequate Net Positive 6.9 Safety Systems 6.10 All nuclear power 6.11 All holders of OLs 6.12 All holders of OLe 6.13 All holders of OLt 6.14 All holders of OLs 6.15 All holders of OLt 6.16 All holders of OLs 6.17 All holders of OLS 6.18 Failure of Westinghouse 6.19 DCpressurization of Reactor 6.20 Degradation of Reactor 6.21 Cool2nt Syst Pressure 6.22 UNITED STATES 6.23 WASHINGTON, D.C. 20555 6.24 IPOSTAGE 6 FEES PAOID 6.25 Division of Operational Events Assessment 6.26 Vern Hodge, NRR 6.27 List of Recently Issued NRC Information Notices 6.28 Charles E. Rossi, Director 6.29 Office of Nuclear Reactor Regulation 6.30 Vern Hodge, NRR 6.31 List of Recently Issued NRC 6.32 Information Notices 6.33 Charles E. Rossi, Director 6.34 Office of Nuclear Reactor Regulation 6.35 Vern Hodge, NRR 6.36 List of Recently Issued NRC Information Notices 6.37 DOEA by DEST in a 6.38 Charles E. Rossi, Director 6.39 Office of Nuclear Reactor Regulation 6.40 Vern Hodge, NRR 6.41 List of Recently Issued NRC Information Notices
UNITED STATES NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON D.C.
20555
December 23, 1987 NRC INFORMATION NOTICE NO. 87-65: PLANT OPERATION BEYOND ANALYZED
CONDITIONS
Addressees All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose This information notice is being provided to alert addressees to potential
problems resulting from operating a plant beyond its analyzed basis.
The
safety concerns of the particular circumstances described in this information
notice are high temperature inside containment and insufficient post-LOCA
cooling of safety systems. It is expected that recipients will review the
information for applicability to their facilities and consider actions, as
appropriate, to avoid similar problems.
However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no
specific action or written response is required.
Description of Circumstances Arkansas 1 (ANO-1). During normal operation on August 7, 1987, it was found
that the containment temperatures were significantly higher than the tempera- tures assumed in the accident analyses in the final safety analysis report
(FSAR , including updates) and equipment qualification program. In the FSAR ,
a design temperature of 110OF was assumed for safety analysis of containment
integrity and 1201F was assumed for equipment qualification during normal
service life. Measured temperatures ranged from 103OF to 1650F with one local
"hot spot" of 1831F about the "A" steam generator . The licensee had observed
such temperatures since plant startup in 1974.
Crystal River 3. During an inspection, it was found that the temperature of
the ultimate heat sink (UHS ), the Gulf of Mexico, was above the value of 850F
assumed in the FSAR analysis for heat removal capability after a loss-of- coolant accident (LOCA ).
The Technical Specifications (TS) permit a UHS
temperature of 1050F. The plant has been operating within the TS limit but
beyond the design-basis temperature of 850F assumed in the accident analysis.
8712170119 AZ
IN 87-65 December 23, 1987 Discussion:
l, Because'ANO-1 had been operating at elevated containment temperatures for
extended periods, the NRC staff had several concerns:
1. The plant had been operating beyond its analyzed basis with regard to
post-accident (LOCA ) containment performance because the initial condi- tions assumed in the analysis were exceeded.
2. The higher temperature implies accelerated aging of equipment required for
post-accident safe shutdown in accordance with regulation 10 CFR 50.49 on
equipment qualification.
3. The higher temperature may cause deterioration of the concrete structure.
In response to the NRC staff concerns, the licen'see submitted an analysis of
the safety implications of the elevated containment temperatures and identified
both near term and long term actions to justify continued operation.
In general, the FSAR contains design bases, operational limits, and analyses of
structures, systems, and components for ensuring the safety of the facility.
It is a statement-by the applicant/licensee of how it intends to comply with
NRC requirements.
This statement is reviewed by the NRC to form the bases for
the operating license.
The analysis of containment performance following a -
design-hasis accidet (for-example, a4LOCA) depands-on-certal-n-assumed-Thit-al---
conditions.
Exceeding these conditions may invalidate the analysis and thereby
raise concerns regarding the maintenance of containment integrity following an
accident.
In accordance with the "100C rule," which may be used to calculate qualified
life, an increase of 100C (180F) over the initially assumed temperature reduces
the qualified life by 50 percent.
Under these circumstances, equipment that is relied on in the event of a design-basis accident may not reliably perform
its safety function when required.
In the case of Crystal River 3, the concern was consistency between the FSAR
and the TS.
Regulation 10 CFR 50.36 requires that the TS be derived from the
analyses in the safety analysis report.
Since the plant has been operating beyond the assumed design-basis temperature for the UHS , the adequate transfer
of post-accident heat loads from safety-related structures, systems, and
components was in question.
Attachment
IN 67-65
December 23, 1987 face 1 of I
LIST OF RECENTLY
ISSUED
NRC
INFORWATION NOTICES 1387 I--_s
. ..
Notice No.
Sublect
87464
Conviction for Falsatication of Security Training Redords
67-35, Supp. 1 Reactor Trip Breaker
Westinghouse Nodal OS-416,
- Failed to Open On Manual
Initiation From the Control Room
87-63
Inadequate Net Positive Suction Hoed in Low Pressure
Safety Systems 87-62
1echanical Failure of
Indicating-Type Fuses
Isuenev
Issued to
22/22/67
All nuclear power reactor facilities
holding an OL or CP
and ll major fuel
facility licensews
12/26/87
All holders of OLs or Cps for nuclear
,ower reactors.
11/9/87
All holders of OLe or CPs for nuclear
por reactors.
12/6/67
All holders of OLt or CP for nuclear
power reactors.
1l167
All holders of OLs or CPs for nuclear
power reactors.
12/4/67
All holders of OLt or CPs for PWRs .
l1/97
All holders of OLs or CPs for nuclear
power reactors.
21117/87
All holders of OLS or cps for nuclear
power reactors.
87-61
Failure of Westinghouse W-2-Type Circuit Breaker
Coll Switches.
87-60
DCpressurization of Reactor Coolant systems In
Pressuri od-Water Reactors
65-lo0.
Degradation of Reactor Supp.
Cool2nt Syst Pressure 0oundary Iesulting from
6oric Acid Corrosion
87-59 Potential RHR
Punp Loss
OL : Operating License
CP
UNITED STATES NUCLEAR REGULATORY COMMISSION
WASHINGTON, D.C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
IPOSTAGE 6 FEES PAOID IN 87-65 December 23, 1987 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 below or the Regional Administrator of the appropriate regional office.
ar es E. Rossi, Director
Division of Operational Events Assessment Office of Nuclear Reactor Regulation
Technical Contacts:
C. Li, NRR
(301) 492-9414
Vern Hodge, NRR (301) 492-8196
. Attachment:
List of Recently Issued NRC Information Notices MI
o
1 '!! i
U1 tLS c..3 11I,;- . .
_ ~-::
i
. .
.<._I:,\\_
,:
-
I
_n~.-
.:
IN 87-65 December 23, 1987 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 below or the Regional Administrator of the appropriate regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contacts:
C. Li, NRR
(301) 492-9414
Vern Hodge, NRR (301) 492-8196 Attachment:
List of Recently Issued NRC The draft of this information notice was
memorandum from L. Shao dated 10/26/87.
Information Notices I
transmitted to DOEA by DEST in a
SEE PREVIOUS CONCURRENCES 'PPMB:ARM
CVHodge
TechEd
11/27/87
12/11/87
AThadani
12/13/87
,C/OGCB: DOEA: NRR
CHBerlinger
12/16/87
IN 87-XX
December xx, 1987 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 below or the Regional Administrator of the appropriate regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contacts:
C. Li, NRR
(301) 492-9414
Vern Hodge, NRR (301) 492-8196 Attachment:
List of Recently Issued NRC Information Notices The draft of this information notice was transmitted to
memorandum from L. Shao dated 10/26/87.
SEE PREVIOUS CONCURRENCES s
i0
PPMB:ARM
SAD/DEST:NRR
C/OGCB:DOEi
CVHodge
TechEd6 AThadani
CHBerlingei
11/27/87
121/i /87 12/1 /87
12//a/87
DOEA by DEST in a k:NRR
r
D/DOEA:NRR
CERossi
12/ /87
IN 87-XX
November xx, 1987 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 below or the Regional Administrator of the appropriate regional office.
Charles E. Rossi, Director Division of Operational Events Assessment
Office of Nuclear Reactor Regulation Technical Contacts:
C. Li, NRR
(301) 492-9414
Vern Hodge, NRR (301) 492-8196 Attachment:
List of Recently Issued NRC Information Notices a
OGCB:DOEA:NRR
CVHodge
1 1/j1/87 PPMB:ARM
TechEd
11/ /87 C/OGCB: DOEA:NRR
CHBerlinger
11/ /87 D/DOEA:NRR
CERossi
11/ /87
list Information Notice 1987-02, Inadequate Seismic Qualification of Diaphragm Valves by Mathematical Modeling and Analysis 13 January 1987 Topic Boric Acid Overspeed trip Information Notice 1987-03, Segregation of Hazardous and Low-Level Radioactive Wastes 15 January 1987 Topic Boric Acid Overspeed trip Information Notice 1987-04, Diesel Generator Fails Test Because of Degraded Fuel 16 January 1987 Topic Boric Acid Coatings Information Notice 1987-05, Miswiring in a Westinghouse Rod Control System 2 February 1987 Topic Unanalyzed Condition Boric Acid Information Notice 1987-06, Loss of Suction to Low-Pressure Service Water System Pumps Resulting from Loss of Siphon 30 January 1987 Topic Boric Acid Information Notice 1987-07, Quality Control of Onsite Dewatering/Solidification Operations by Outside Contractors 3 February 1987 Topic Boric Acid Process Control Program Information Notice 1987-08, Degraded Motor Leads in Limitorque DC Motor Operators 4 February 1987 Topic Boric Acid Anchor Darling Information Notice 1987-09, Emergency Diesel Generator Room Cooling Design Deficiency 5 February 1987 Topic Probabilistic Risk Assessment Loss of Offsite Power Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps 11 February 1987 Topic Loss of Offsite Power Water hammer Information Notice 1987-11, Enclosure of Vital Equipment within Designated Vital Areas 13 February 1987 Topic Contraband Water hammer Information Notice 1987-11, Enclosure of Vital Equipment Within Designated Vital Areas 13 February 1987 Topic Contraband Water hammer Information Notice 1987-12, Potential Problems with Metal Clad Circuit Breakers, General Electric Type AKF-2-25 13 February 1987 Information Notice 1987-13, Potential for High Radiation Fields Following Loss of Water from Fuel Pool 24 February 1987 Topic Water hammer Information Notice 1987-14, Actuation of Fire Suppression System Causing Inoperability of Safety-Related Ventilation Equipment 23 March 1987 Topic Water hammer Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223b of the Atomic Energy Act of 1954, as Amended 25 March 1987 Topic Basic Component Information Notice 1987-15, Compliance with the Posting Requirements of Subsection 223B of the Atomic Energy Act of 1954, As Amended 25 March 1987 Topic Basic Component Information Notice 1987-16, Degradation of Static O Ring Pressure Switches 2 April 1987 Topic Commercial Grade Information Notice 1987-17, Response Time of Scram Instrument Volume Level Detectors 7 April 1987 Topic Scram Discharge Volume Water hammer Information Notice 1987-18, Unauthorized Service on Teletherapy Units by Nonlicensed Maintenance Personnel 8 April 1987 Topic Water hammer Information Notice 1987-19, Perforation and Cracking of Rod Cluster Control Assemblies 9 April 1987 Information Notice 1987-20, Hydrogen Leak in Auxiliary Building 20 April 1987 Topic Excess Flow Check Valve Information Notice 1987-21, Shutdown Order Issued Because Licensed Operators Asleep While on Duty 11 May 1987 Topic Inattentive Information Notice 1987-22, Operator Licensing Requalification Examinations at Nonpower Reactors 22 May 1987 Topic License Renewal Information Notice 1987-23, Loss of Decay Heat Removal During Low Reactor Coolant Level Operation 27 May 1987 Topic Reactor Vessel Water Level Information Notice 1987-24, Operational Experience Involving Losses of Electrical Inverters 4 June 1987 Information Notice 1987-25, Potentially Significant Problems Resulting from Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events 11 June 1987 Topic Boric Acid Fire Watch Overspeed Information Notice 1987-25, Potentially Significant Problems Resulting From Human Error Involving Wrong Unit, Wrong Train, or Wrong Component Events 11 June 1987 Topic Boric Acid Fire Watch Overspeed Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter UF6 Cylinders 11 June 1987 Topic Boric Acid Information Notice 1987-26, Cracks in Stiffening Rings on 48-Inch-Diameter Uf6 Cylinders 11 June 1987 Information Notice 1987-27, Iranian Official Implies Vague Threat to U.S. Resources 10 June 1987 Information Notice 1987-28, Air Systems Problems at U.S. Light Water Reactors 28 December 1987 Topic Boric Acid Information Notice 1987-29, Recent Safety-Related Incidents at Large Irradiators 26 June 1987 Topic Coatings Temporary Modification Biofouling Uranium Hexafluoride Information Notice 1987-30, Cracking of Surge Ring Brackets in Large General Electric Company Electric Motors 2 July 1987 Information Notice 1987-31, Blocking Bracing, and Securing of Radioactive Materials Packages in Transportation 10 July 1987 Topic Uranium Hexafluoride Information Notice 1987-32, Deficiencies in the Testing of Nuclear-Grade Activated Charcoal 10 July 1987 Information Notice 1987-33, Applicability of 10 CFR Part 21 to Nonlicensees 24 July 1987 Topic Commercial Grade Basic Component Information Notice 1987-34, Single Failures in Auxiliary Feedwater Systems 24 July 1987 Information Notice 1987-35, Reactor Trip Breaker, Westinghouse Model DS-416, Failed to Open on Manual Initiation from the Control Room 30 July 1987 Information Notice 1987-36, Significant Unexpected Erosion of Feedwater Lines 4 August 1987 Information Notice 1987-37, Compliance with the General License Provisions of 10 CFR Part 31 10 August 1987 Information Notice 1987-39, Control of Particle Contamination at Nuclear Power Plants 21 August 1987 Topic Fuel cladding Overexposure Information Notice 1987-40, Backseating Valves Routinely to Prevent Packing Leakage 31 August 1987 Topic Packing leak Information Notice 1987-41, Failures of Certain Brown Boveri Electric Circuit Breakers 31 August 1987 Information Notice 1987-42, Diesel Generator Fuse Contacts 4 September 1987 Information Notice 1987-43, Gaps in Neutron-Absorbing Material in High-Density Spent Fuel Storage Racks 8 September 1987 Information Notice 1987-44, Thimble Tube Thinning in Westinghouse Reactors 16 September 1987 Information Notice 1987-45, Recent Safety-Related Violations of NRC Requirements by Industrial Radiography Licensees 25 September 1987 Topic High Radiation Area Overexposure Information Notice 1987-46, Undetected Loss of Reactor Coolant 30 September 1987 Information Notice 1987-48, Information Concerning the Use of Anaerobic Adhesive/Sealants 9 October 1987 Topic Loctite Information Notice 1987-49, Deficiencies in Outside Containment Flooding Protection 9 October 1987 Topic Safe Shutdown ... further results