Deficiencies in Upgrade Programs for Plant Emergency Operating ProceduresML031250068 |
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: |
08/14/1986 |
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From: |
Jordan E NRC/IE |
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To: |
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References |
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IN-86-064, NUDOCS 8608120028 |
Download: ML031250068 (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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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>. |
118 ORIGINAL UNITED STATES
IN No.:
86-64 SSINS 6835 NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
WASHINGTON, DC 20555 August 14, 1986 IE INFORMATION NOTICE NO. 86-64: DEFICIENCIES IN UPGRADE PROGRAMS FOR
PLANT EMERGENCY OPERATING PROCEDURES
Addressees
All nuclear power reactor facilities holding an operating license or a
construction permit.
Purpose
This notice is to alert recipients to problems found in reviews and audits of
Procedures Generation Packages (PGPs) and emergency procedures for operating
reactors and license applicants. Indications are that many utilities have not
apropriately developed or implemented upgraded emergency operating procedures
(EOPs). Deficiencies have been identified in the development and implementation
of each of the four major aspects of the upgrade programs for utility procedures.
It is expected that recipients will review the information for applicability
to their facilities and consider actions, if appropriate, to preclude similar
problems occurring at their facilities. However, suggestions contained in this
notice do not constitute NRC requirements; therefore, no specific action or
written response is required.
Background:
As required by the TMI Action Plan, NUREG-0737, the industry developed
technical guidelines based on re-analysis of transients and accidents to
support upgrading EOPs. In addition, the staff developed a long range program
for upgrading EOPs in the industry. Development and implementation of upgraded
EOPs were requested by the NRC staff in Generic Letter 82-33, (NUREG-0737, Supplement 1, Requirements for Emergency Response Capability), pursuant to
10 CFR 50.54f. "Guidelines for the Preparation of Emergency Operating
Procedures" (NUREG-0899), was identified as the reference guidance document
for the EOP upgrade effort.
NUREG-0737, Supplement 1, specifies submittal of a PGP that describes a
licensee's program for upgrading and implementing EOPs by addressing four
ma4or areas: the technical bases of the procedures, the procedures writer's
guide, the program for validation of the procedures, and the operator training
program for the upgraded procedures. The NRC staff had planned to review and
approve generic technical guidelines and plant-specific PGPs and had not
planned to routinely review,the EOPs. The PGP review may be performed after
8608120028
IN 86-64
.'- i August 14, 1986 an operating reactor has implemented its upgraded EOPs so as not to delay their
implementation. PGPs for applicants are reviewed as part of their FSAR submittal
before licensing. The PGP review for operating reactors and applicants is
conducted in accordance with NUREG-0800, Standard Review Plan, Section 13.5.2, revised July 1985. PGPs for 89 plants have been received by the staff, 79 have
been implemented by plants, and reviews of PGPs for 48 plants have been conducted.
Description of Circumstances
The NRC staff has collected information on the quality of the upgraded EOPs
throughout the industry. This information has come from several sources
including: (1) in depth audits of EOP upgrade programs at four plants, (2)
reviews of PGPs, (3) the review of procedures as a part of operating event
analyses, (4) reviews of detailed control room design review program plans and
summary reports, (5) examiners' experiences during operator license examinations,
(6) industry comments on procedure-related research efforts, and (7) other
interactions with licensees. The assessment of this information indicates that
significant deficiencies in implementing the EOP upgrade programs exist.
Specifically:
1. Licensees have not followed commitments they made in their PGPs. That is, the emergency operating procedures, the verification and validation program, and/or the operator training program was not found to adequately adhere to
the PGP at any of the four plants audited.
2. Undocumented deviations from the Owners Groups' generic technical guidelines J
have been found at all four plants audited. Deviations are expected, but
Generic Letter 82-33 requests that they be identified, and a technical
justification provided in the PGP. In addition, programs have been found
deficient where deviations were identified after the PGP had been submitted, reviewed and approved by the NRC. NUREG-0899 provides guidance in processing
sUch deviations.
3. Failures to appropriately adapt the Owners Groups' generic technical guide- lines have been found at some of the plants audited. There are also
instances in which the generic technical guidelines are technically
inappropriate to the particulars of individual plants so that deviations
are necessary but have not been made in the emergency operating procedures
and/or documented in the PGP or plant records. In addition, some licensees
have neither adopted nor deviated from the generic technical guidelines, but
have used them verbatim as emergency operating procedures. The NRC review
and approval of the generic technical guidelines has been limited to assessing
their suitability as technical guidelines; not as procedures for typical
plants.
4. Failures to adhere to the PGP writer's guide have been found at all four
plants audited. The purpose of following an approved writer's guide is
to assure that potentially confusing or error-prone writing styles, nonmenclature, formats, conventions, or inconsistencies are avoided.
Failure to adhere to the approved writer's guide in the PGP has resulted
in instances of safety significant problems in the EOPs at some of the
plants audited.
IN 86-64 August 14, 1986 5. Failures to adhere to PGP commitments on the verification and validation
(V&V) of emergency operating procedures have been found at all plants
audited. The implementation of V&V programs has not been successful in
identifying and correcting the types of deficiencies cited in this notice
at any of the plants audited. Approved PGPs generally include commitments
to use multidisciplinary teams in conducting the V&V programs. Single
individuals rather than multidisciplinary teams performed the V&V function
at most plants audited.
6. Training programs at some plants audited have been found deficient in areas
such as (a)providing adequate instruction in the philosophy behind the
function orientation of upgraded EOPs, (b) training all operators on all
EOPs before they are implemented, and (c) evaluating operator knowledge
and performance after they have received training on the upgraded EOPs.
Discussion:
While the above findings do not necessarily represent the situation at any single
plant, their occurrence across the plants contacted suggests that the overall
quality of EOPs may not meet the requirements of NUREG-0737, Supplement 1, and
may need to be Improved. To address these potentially safety significant
deficiencies, the NRC staff is (1) issuing this information notice to alert
licensees to the deficiencies, (2) continuing the audit program on a priority
basis to determine the scope and safety significance of these deficiencies, and
(3) planning inspections at all plants to evaluate the implementation of the
licensees' commitments to develop and implement upgraded EOPs.
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 NRC regional office or this office.
Jordan, Director
Divisio f Emergency Preparedness
and E gineering Response
Office of Inspection and Enforcement
Technical Contacts: J. Bongarra, NRR
(301) 492-4882 W. G. Kennedy, NRR
(301) 492-4578 H. Bailey, IE
(301) 492-9006 Attachment: List of Recently Issued IE Information Notices
Attachment a
IN 86-64 August 14, 1986 LIST OF RECENTLY ISSUED
IE INFORMATION NOTICES
information Date of
Notice No. Subject Issue Issued to
86-63 Loss Of Safety Injection 8/6/86 All PWR facilities
Capability holding an OL or CP
86-62 Potential Problems In West- 7/31/86 All power reactor
inghouse Molded Case Circuit facilities holding
Breakers Equipped With A an OL or CP
Shunt Trip
86-61 Failure Of Auxiliary Feed- 7/28/86 All power reactor
water Manual Isolated Valve facilities holding
a CP
86-60 Unanalyzed Post-LOCA Release 7/28/86 All power reactor
Paths facilities holding
an OL or CP
86-31 Unauthorized Transfer And 7/14/86 All NRC general
Sup. 1 Loss Of Control Of Industrial licensees that possess
Nuclear Gauges and use industrial
nuclear gauges
86-59 Increased Monitoring Of 7/14/86 All NRC licensees
Certain Patients With authorized to use
Implanted Coratomic, Inc. nuclear-powered
Model C-100 and C-101 cardiac pacemakers
Nuclear-Powered Cardiac
Pacemakers
86-58 Dropped Fuel Assembly 7/11/86 All power reactor
facilities holding
an OL or CP
86-57 Operating Problems With 7/11/86 All power reactor
Solenoid Operated Valves At facilities holding
Nuclear Power Plants an OL or CP
86-56 Reliability Of Main Steam 7/10/86 All PWR facilities
Safety Valves holding an OL or CP
86-55 Delayed Access To Safety- 7/10/86 All power reactor
Related Areas And Equipment facilities holding
During Plant Emergencies an OL or CP
XL = Operating License
CD = 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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