Status of NRC Staff'S Review of BWRVIP-05ML031050170 |
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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
08/07/1997 |
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From: |
Slosson M Office of Nuclear Reactor Regulation |
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To: |
|
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References |
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IN-97-063, NUDOCS 9708070078 |
Download: ML031050170 (10) |
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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, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </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 [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
K>_
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555-0001 August 7, 1997 NRC INFORMATION NOTICE 97-63: STATUS OF NRC STAFF'S REVIEW OF
BWRVI P-05
Addressees
All holders of operating licenses or construction permits for boiling water reactors (BWRs).
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information notice to inform
addressees about the status of NRC staffs review of "BWR Vessel and Internals Project, BWR Reactor Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05)."
This information notice does not transmit or imply any new or changed requirements or staff
positions. No specific action or written response is required.
Discussion
On May 12, 1997, the NRC staff and members of the Boiling Water Reactor Vessel and
Internals Project (BWRVIP) met with the Commission to discuss the NRC staffs review of
the BWRVIP's proprietary report, "BWR Vessel and Internals Project, BWR Reactor
Pressure Vessel Shell Weld Inspection Recommendations (BWRVIP-05)," dated
September 28, 1995. This report questions the extent of augmented reactor vessel
inspection required in 10 CFR Part 50, 50.55a(g)(6)(ii)(A)(2). In accordance with guidance
provided by the Commission following that meeting, in Staff Requirements Memorandum
(SRM) M970512B, dated May 30, 1997, the staff has initiated a broader, risk-informed
review of the BWRVIP-05 proposal. Further, the final safety evaluation report (SER) will
need to be reviewed by the Advisory Committee on Reactor Safeguards (ACRS) prior to
issuance. Based on the NRC staffs review of the BWRVIP-05 report, the staff has
concluded that the industry's assessment does not sufficiently address risk, and additional
work is necessary to provide a complete risk-informed evaluation. Therefore, the NRC
staffs current estimate is that completion of this effort, including industry input and ACRS
review, will take approximately six months.
One result of the additional review performed to date was the identification of a transient at
a foreign BWR of U.S. design in which the reactor pressure vessel (RPV) was subjected to
high pressure at a low temperature. This cold over-pressure transient was not included as
a design-basis event for BWRs nor was it considered from a risk perspective in the
BWRVIP-05 report. However, the recognition of this transient has led the staff to determine
that cold over-pressure transients are of sufficient safety significance that they heed to be
addressed PDrt Sores 9'-O2IE 9?°f 7
9708070 78 IJIIMIIIIIIgIIIIIIIIIIJIIIIiJII
LI~ gll f SS1i
- S -
IN 97- 63 August 7, 1997 as part of the BWRVIP-05 review. Therefore, the staff intends to request an industry
evaluation of the potential for, and consequences of, nondesign-basis events which were not
addressed in the BWRVIP-05 submittal.
In order for the additional analysis requested by the Commission to be completed and
reviewed, the staff will consider technically-justified requests for reliefs from the
augmented examination in accordance with 10 CFR 50.55a(a)(3)(i), 10 CFR 50.55a(a)(3)(ii),
and 50.55a(g)(6)(ii)A(5) from BWR licensees who are scheduled to perform inspections of the
BWR RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-justified reliefs would be considered for inspection delays of up to two operating
cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their reqgred inspections of "essentially 100 pertr of all axial welds.;,
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its
review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell
welds are necessary, any licensee who seeks and receives schedular relief will be required
to perform the inspections at the first reasonable opportunity.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate NRC Regional Office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of IsecenIsued NRC Information Notice
K>
K>
1-1_
Attachment
IN 97-63 August 7, 1997 LIST OF RECENTLY ISSUED
NRC INFORMATION NOTICES
Information Date of
Notice No. Subject Issuance Issued to
97-62 Unrecognized Reactivity 08/06/97 All holders of OLs or CPs
Addition During Plant for nuclear power reactors
Shutdown
97-61 U.S. Department of 08/06/97 All U.S. Nuclear Regulatory
Health and Human Commission medical licensees, Services Letter, to veterinarians, and manu- Medical Device Manu- facturers/distributors of
facturers, on the medical devices
Year 2000 Problem
97-60 Incorrect Unreviewed 08/01/97 All holders of OLs or CPs
Safety Question Deter- for pressurized-water
mination Related to reactors
Emergency Core Cooling
System Swapover from
the Injection Mode to
the Recirculation Mode
97-59 Fire Endurance Test 08/01/97 All holders of OLs or CPs
Results of Versawrap for nuclear power reactors
Fire Barriers
97-58 Mechanical Intejrity of 07/31/97 Holders of and Applicants
In-Situ Leach Injection for Licenses for In-Situ
Wells and Piping Leach Facilities
97-57 Leak Testing of Packaging 07/30/97 Suppliers and users of
Used in the Transport of packaging for the trans- Radioactive Material portation of radioactive
material required to per- form packaging leak tests
OL = Operating License
CP = Construction Permit
IN 97- 63 August 7, 1997 as part of the BWRVIP-05 review. Therefore, the staff intends to request an industry
evaluation of the potential for, and consequences-of, nondesign-basis events which were not
addressed in the BWRVIP-05 submittal.
In order for the additional analysis requested by the Commission to be completed and
reviewed, the staff will consider technically-justified requests for reliefs from the
augmented examination in accordance with 10 CFR 50.55a(a)(3)(i), 10 CFR 50.55a(a)(3)(ii),
and 50.55a(g)(6)(ii)A(5) from BWR licensees who are scheduled to perform inspections of the
BWR RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptablyjustified reliefs would be considered for inspection delays of up to two operating
cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their required inspections of "essentially 100 percent" of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its
review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell
welds are necessary, any licensee who seeks and receives schedular relief will be required
to perform the inspections at the first reasonable opportunity.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate NRC Regional Office.
original signed by S.H. Weiss for
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Information Notice
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: S:%DRMPSEC1ADMLTR.TER To receve a copy of this docutment, Indicate in the box C=Copy wlo
attachment/enclosure E=Copy with attachmenUendosure N = No copy
CONTACT
S D:DE l OGC CRGR l
CECarpenter* BWSheron* JMoore*.I
07/14197 07121/97 08101/97 08/05/97 C:PECB (A)D:DRPM 1 AChaffee ytJ MMSlosson j
6V¶4/97 0f/p/97 07/ /97 7/ /97 OFFICIAL RECORD COPY
IN 97- August , 1997 as part of the BWRVIP-05 review. Therefore, the staff intends to request an industry
evaluation of the potential for, and consequences of, nondesign-basis events which were not
addressed in the BWRVIP-05 submittal.
In order for the additional analysis requested by the Commission to be completed and
reviewed, the staff will consider technically-justified requests for reliefs from the
augmented examination In accordance with 10 CFR 50.55a(a)(3)(i), 10 CFR 50.55a(a)(3)(ii),
and 50.55a(g)(6)(ii)A(5) from BWR licensees who are scheduled to perform inspections of the
BWR RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-justified reliefs would be considered for inspection delays of up to two operating
cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their required inspections of "essentially 100 percent" of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its
review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell
welds are necessary, any licensee who seeks and receives schedular relief will be required
to perform the inspections at the first reasonable opportunity.
This information notice requires no specific action or written response. If you have any
questions about the information in this notice, please contact the person listed below or the
appropriate NRC Regional Office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical contact: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Information Notice
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: S:%DRMPSEC1ADMLTR.TER To receive a copy of this document, indicate inthe box C=Copy wlo
attachment/enclosure E=Copy with attachment/enclosure N = No copy
CONTACT
S D:DE J OGC CRGR L
CECarpenter* BWSheron* JMoore* P; -
4 C i vyd4e
07/14/97 107/21/97 08/01/97 ;X /97 C:PECB (A)D:DRPM l
AChaffee MMSlosson
07/ /97 [07/ /97 07/ /97 7/ /97 OFFICIAL RECORD COPY
- xx-97 August, 1997 as part of the BWRVIP-05 review. Therefore, the staff intends to request an industry
evaluation of the potential for, and consequences of, nondesign-basis events which were not
addressed in the BWRVIP-05 submittal.
In order for the additional analysis requested by the Commission to be completed and
reviewed, the staff will consider technically-justified requests for reliefs from the
augmented examination in accordance with 10 CFR 50.55a(a)(3)(i), 10 CFR 50.55a(a)(3)(ii),
and 50.55a(g)(6)(ii)A(5) from BWR licensees who are scheduled to perform inspections of the
BWR RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-ustified reliefs would be considered for inspection delays of up to two operating
cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their required inspections of "essentially 100 percent" of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its
review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell
welds are necessary, any licensee who seeks and receives schedular relief will be required
to perform the inspections at the first reasonable opportunity.
This administrative letter requires no specific action or written response. If you have any
questions about the information in this letter, please contact the person listed below or the
appropriate NRC Regional Office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Contact: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Administrative Letters
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: S:1DRMPSEC1ADMLTR.TER To receive acopy of this document, indicate in the box C=Copy wlo
attachmentlenclosure E=Copy with asachment/endosure N = No copy
CONTACT
S D:DE OGC CRGR
CECarpenter* BWSheron* JMooreI
07/14/97 07/21/97 08/01/97 07/ /97 lC:PECB (A)D:DRPM
AChaffee MMSlosson
07/ 197 07/ /97 07/ /97 7/ 197 OFFICIAL RECORD COPY
} 11_
AL xx-97 July xx, 1997 as part of the BWRVIP-05 review. Therefore, the staff intends to request an industry
evaluation of the potential for, and consequences of, nondesign-basis events which were not
addressed in the BWRVIP-05 submittal.
In order for the additional analysis requested by the Commission to be completed and
reviewed, the staff will consider technically-justified requests for reliefs from the
augmented examination in accordance with 10 CFR 50.55a(a)(3)(i) and 10 CFR
50.55a(a)(3)(ii) from BWR licensees who are scheduled to perform inspections of the
BWR RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-justified reliefs would be considered for inspection delays of up to two operating
cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their required inspections of "essentially 100 percent" of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its
review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell
welds are necessary, any licensee who seeks and receives schedular relief will be required
to perform the inspections at the first reasonable opportunity.
This administrative letter requires no specific action or written response. If you have any
questions about the information in this letter, please contact the person listed below or the
appropriate NRC Regional Office.
Marylee M. Slosson, Acting Director
Division of Reactor Program Management
Office of Nuclear Reactor RegulatioZ
Contact: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Administrative LettersH
- SEE PREVIOUS CONCURRENCES
DOCUMENT NAME: S:\DRMPSEC\ADMLTR.TER To receive a copy of ths document, Indicate in the box C=Copy wlo
attachmentlenclosure E=Copy with attachmentlendosure N = No copy 7
CONTACT
S D:DE OGC CRGR
CECarpenter' BWSheron*'AD4Ak/I&
07/14/97 07/21/97 / 071 197
__197 C:PECB (A)D:DRPM
AChaffee MMSlosson l
07197 07/ 197 07 RE D CY 71 /97 OFF~ICIAL RECORD COPY
AL xx-97 July xx, 1997 augmented examination in accordance with 10 CFR 50.55a(a)(3)(i) and 10 CFR
50.55a~a)(3)(ii) from BWR licensees who are scheduled to perform inspections of the BWR
RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-justified reliefs would be considered for inspection delays of up to two
operating cycles for BWR RPV circumferential shell welds only. Licensees will still need to
perform their required inspections of 'essentially 100 percent' of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of the
availability of inspection equipment and the need for licensees to reschedule inspections if
they should be deemed necessary upon completion of the risk-informed evaluation.
Licensees should be aware that if the NRC staff determines at the conclusion of its review
of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell welds
are necessary, any licensee who seeks and receives schedular relief will be required to
perform the inspections at the first reasonable opportunity.
This administrative letter requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate NRC Regional Office.
Marylee M. Slosson, Director
Division of Reactor Program Management
Office of Nuclear Reactor
Technical Contacts: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Administrative Letters
DOCUMENT NAME: S:\DRMP SEC\ADMLTR.TER To receive a copy of this document, indicate in the box C-Copy w/o
attachment/enclosure E -Copy with attachment/enclosure N - No copy
CONTACT
S _D: __ OGC CRGR
CECarpenter EWSI3n
07/14/97 0701297 07/ 071_97_97 C:PECB _ (A)D!DRPM
AChaffee MMSlosson
07/ /97 07/ /97 7/ /97 OFFICIAL RECORD COPY
AL xx-97 July xx, 1997 augmented examination in accordance with 10 CFR 50.55a(a)(3)(i) and 10 CFR
50.55a(a)(3)(ii) from BWR licensees who are scheduled to perform inspections of the BWR
RPV circumferential shell welds during the Fall 1997 or Spring 1998 outage seasons.
Acceptably-justified reliefs would be considered for inspection delays of up to two
operating cycles for BWR RPV circumferential shell welds only. Licensees will still need to
perform their required inspections of 'essentially 100 percent" of all axial welds.
Granting reliefs for 40-months or two operating cycles is based on the consideration of
consideration of the availability of inspection equipment and the need for licensees to
reschedule inspections if they should be deemed necessary upon completion of the risk- informed evaluation. The-acceptability of plant-specific relief requests would be based on
a determination that any risk from failure of circumferential welds would not be significant
until later in plant life when high fluence values are reached. Licensees should be aware
that if the NRC staff determines at the conclusion of its review of the BWRVIP-05 proposal
that inspections of the BWR RPV circumferential shell welds are necessary, any licensee
who seeks and receives schedular relief will be required to perform the inspections at the
first reasonable opportunity.
This administrative letter requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate NRC Regional Office.
Marylee M. Slosson, Director
Division of Reactor Program Management
Office of Nuclear Reactor
Technical Contacts: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Administrative Letters
DOCUMENT NAME: S:\DRMP SEC\ADMLTR.TER To receive acopy of this document, indicate in the box c-copy w/o
attachment/enclosure E -Copy with attachment/enclosure N - No copy
CONTACT
S l D:DE ,*t1\ b OGC lCRGRll
CECarpenter BWSheron
07/14/97 07/ /97 07/ /97 07/ /97 C:PECB l (A)D:DRPM
AChaffee MMSosson l
07/ /97 07/ /97 07 RECRD9OP 7/ 197
- . I 4 4 K`>_
A xx-97 July xx, 1997 cycles for BWR RPV circumferential shell welds only. Licensees will still need to perform
their required Inspections of "essentially 100 percent" of all axial welds. Licensees should be
aware that if the NRC staff determines at the conclusion of its review of the BWRVIP-05 proposal that inspections of the BWR RPV circumferential shell welds are necessary, any
licensee who seeks and receives schedular relief will be required to perform the inspections
at the first reasonable opportunity.
This administrative letter requires no specific action or written response. If you have any
questions about the information in this notice, please contact one of the technical contacts
listed below or the appropriate NRC Regional Office.
Marylee M. Slosson, Director
Division of Reactor Program Management
Office of Nuclear Reactor
Technical Contacts: C. E. Carpenter, NRR
301-415-2169 E-mail: cec@nrc.gov
Attachment: List of Recently Issued NRC Administrative Letters
DOCUMENT NAME: S:MDRMPSEC\ADMLTR.TER
To receive a copy of this document, indicate in the box C=Copy wio attachmentienclosure E=Copy with attachmentiendosure N = No copy
OFFICE
CONTACT
S I /$D:DE I OGC I CRGR l
NAME CCarpenter &e, BSheron
RDenniDE97 P L-979 DATE 17/J97 7//7 7//97 7/9I7 v r
OFFICE C:PECB I (A)D:DRPM I
NAME AChaffee l MMSlosson
DATE 71 /97 _7/ /97
4 A,
UI-HUIAL KCLORKlJ WOPY
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list | - Information Notice 1997-01, Improper Electrical Grounding Results in Simultaneous Fires in the Control Room and the Safe-Shutdown Equipment Room (8 January 1997, Topic: Safe Shutdown, Emergency Lighting)
- Information Notice 1997-02, Cracks Found in Jet Pump Riser Assembly Elbows at Boiling Water Reactors (6 February 1997)
- Information Notice 1997-03, Defacing of Labels to Comply with 10 CFR 20.1904(b) (20 February 1997)
- Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents (24 February 1997, Topic: Backfit)
- Information Notice 1997-05, Offsite Notification Capabilities (27 February 1997, Topic: Earthquake)
- Information Notice 1997-06, Weaknesses in Plant-Specific Emergency Operating Procedures for Refilling the Secondary Side of Dry Once-Through Steam Generators (4 March 1997)
- Information Notice 1997-07, Problems Identified During Generic Letter 89-10 Closeout Inspections (6 March 1997, Topic: Hot Short, Safe Shutdown, Weak link)
- Information Notice 1997-08, Potential Failures of General Electric Magne-Blast Circuit Breaker Subcomponents (12 March 1997, Topic: Coatings, Weak link)
- Information Notice 1997-09, Inadequate Main Steam Safety Valve (MSSV) Setpoints and Performance Issues Associated with Long MSSV Inlet Piping (12 March 1997)
- Information Notice 1997-10, Liner Plate Corrosion in Concrete Containments (13 March 1997)
- Information Notice 1997-11, Cement Erosion from Containment Subfoundations at Nuclear Power Plants (21 March 1997)
- Information Notice 1997-12, Potential Armature Binding in General Electric Type Hga Relays (24 March 1997)
- Information Notice 1997-13, Deficient Conditions Associated with Protective Coatings at Nuclear Power Plants (24 March 1997, Topic: Coatings)
- Information Notice 1997-14, Assessment of Spent Fuel Pool Cooling (28 March 1997, Topic: Time to boil, Coatings)
- Information Notice 1997-15, Reporting of Errors and Changes in Large-Break Loss-of-Coolant Accident Evaluation Models of Fuel Vendors and Compliance with 10 CFR 50. 46(a)(3) (4 April 1997, Topic: Coatings, Fuel cladding)
- Information Notice 1997-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code Inservice Testing or Technical Specification Surveillance Testing (4 April 1997, Topic: Stroke time, Coatings)
- Information Notice 1997-17, Cracking of Vertical Welds in the Core Shroud and Degraded Repair (4 April 1997, Topic: Coatings, Intergranular Stress Corrosion Cracking)
- Information Notice 1997-18, Problems Identified During Maintenance Rule Baseline Inspections (14 April 1997, Topic: Probabilistic Risk Assessment, Coatings, Emergency Lighting)
- Information Notice 1997-19, Safety Injection System Weld Flaw at Sequcyah Nuclear Power Plant, Unit 2 (18 April 1997, Topic: Boric Acid, Thermal fatigue)
- Information Notice 1997-20, Identification of Certain Uranium Hexafluoride Cylinders That Do Not Comply with ANSI N14.1 Fabrication Standards (17 April 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-21, Availability of Alternate AC Power Source Designed for Station Blackout Event (18 April 1997, Topic: Main transformer failure)
- Information Notice 1997-22, Failure of Welded-Steel Moment Resisting Frames During Northridge Earthquake (25 April 1997, Topic: Earthquake)
- Information Notice 1997-23, Evaluation and Reporting of Fires and Unplanned Chemical Reaction Events at Fuel Cycle Facilities (7 May 1997, Topic: Earthquake, Uranium Hexafluoride)
- Information Notice 1997-24, Failure of Packing Nuts on One-Inch Uranium Hexafluoride Cylinder Valves (8 May 1997, Topic: Eddy Current Testing, Uranium Hexafluoride)
- Information Notice 1997-25, Dynamic Range Uncertainties in the Reactor Vessel Level Instrumentation (9 May 1997, Topic: Earthquake)
- Information Notice 1997-26, Degradation in Small-Radius U-Bend Regions of Steam Generator Tubes (19 May 1997, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1997-27, Effect of Incorrect Strainer Pressure Drop on Available Net Positive Suction Head (16 May 1997, Topic: Earthquake)
- Information Notice 1997-28, Elimination of Instrument Response Time Testing Under the Requirements of 10 CFR 50.59 (30 May 1997, Topic: Enforcement Discretion)
- Information Notice 1997-29, Containment Inspection Rule (30 May 1997)
- Information Notice 1997-30, Control of Licensed Material During Reorganizations, Employee-Management Disagreements, and Financial Crises (3 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-31, Failures of Reactor Coolant Pump Thermal Barriers and Check Valves in Foreign Plants (3 June 1997)
- Information Notice 1997-32, Defective Worm Shaft Clutch Gears in Limitorque Motor-Operated Valve Actuators (10 June 1997)
- Information Notice 1997-33, Unanticipated Effect of Ventilation System on Tank Level Indications and Engineering Safety Features Actuation System Setpoint (11 June 1997)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels in Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-34, Deficiencies in Licensee Submittals Regarding Terminology for Radiological Emergency Action Levels In Accordance with the New Part 20 (12 June 1997, Topic: Deep Dose Equivalent)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (Inc) IR100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-35, Retrofit to Industrial Nuclear Company (INC) Ir100 Radiography Camera to Correct Inconsistency in 10 CFR Part 34 Compatibility (18 June 1997)
- Information Notice 1997-36, Unplanned Intakes by Worker of Transuranic Airborne Radioactive Materials and External Exposure Due to Inadequate Control of Work (20 June 1997, Topic: Overexposure)
- Information Notice 1997-37, Main Transformer Fault with Ensuing Oil Spill Into Turbine Building (20 June 1997)
- Information Notice 1997-38, Level-Sensing System Initiates Common-Mode Faulure of High-Pressure-Injection Pumps (24 June 1997, Topic: Hydrostatic)
- Information Notice 1997-39, Inadequate 10 CFR 72.48 Safety Evaluations of Independent Spent Fuel Storage Installations (26 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-40, Potential Nitrogen Accumulation Resulting from Backleakage from Safety Injection Tanks (26 June 1997)
- Information Notice 1997-41, Revised - Potentially Undersized Emergency Diesel Generator (EDG) Oil Coolers (27 June 1997)
- Information Notice 1997-42, Management Weaknesses Resulting in Failure to Comply with Shipping Requirements for Special Nuclear Material (27 June 1997, Topic: Uranium Hexafluoride)
- Information Notice 1997-43, License Condition Compliance (1 July 1997, Topic: Ultimate heat sink)
- Information Notice 1997-44, Failures of Gamma Metrics Wide-Range Linear Neutron Flux Channels (1 July 1997)
- Information Notice 1997-45, Environmental Qualification Deficiency for Cables & Containment Penetration Pigtails (2 July 1997)
- Information Notice 1997-46, Unisolable Crack in High-Pressure Injection Piping (9 July 1997, Topic: Flow Induced Vibration)
- Information Notice 1997-47, Inadequate Puncture Tests for Type B Packages Under 10 CFR 71.73(c)(3) (27 June 1997)
- Information Notice 1997-48, Inadequate or Inappropriate Interim Fire Protection Compensatory Measures (9 July 1997, Topic: Safe Shutdown, Unanalyzed Condition, Fire Barrier, Emergency Lighting, Continuous fire watch, Fire Protection Program, Fire Watch, Operability Assessment)
... further results |
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