ML072780538
| ML072780538 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 07/09/1987 |
| From: | Rossi C Office of Nuclear Reactor Regulation |
| To: | |
| SECY RAS | |
| References | |
| 50-219-LR, AmerGen-Applicant-46, OMB 3150-0011, RAS 14260 BL-87-001 | |
| Download: ML072780538 (7) | |
Text
I*;Lb 0 UJ1. HUoLA ~UA0~ OMSJt In thidwd1?Eg L Co- (W1 D~~~cket ~
ýR N&O-O~
4 Rfficdal FAIbMNo.L..
VRFE6~ by-A
(
nv'Lensee Intervenor________
APPLICANT'S EXHIBIT 46 SSINS No.1 OMB No.:
NRCB 87-0:
6820 3150-O01l U!NITED STATES W"U"AMCLEAR REGULATORY COWISSION
- OrrLCL OF.NUCLEAR REACTOR REGULATION WASHINGTON, D.C.
20555 DOCKETED USNRC October 1, 2007 (10:45am)
OFFICE OF SECRETARY RULEMAKINGS AND ADJUDICATIONS STAFF July 9, 1987 NRC BULLETIN NO. 87-01:
THINNING OF PIPE WALLS IN NUCLEAR POWER PLANTS Addressees:
All licensees for nuclear power plants holding an operating license or a construction permit.
- Purpose:
The purpose of this bulletin is to request that licensees submit information concerning their programs for monitoring the thickness of pipe walls in high-energy single-phase and two-phase carbon steel piping systems.
Description of Circumstances:
On December 9, 1986, Unit 2 at the Surry Power Station experienced a cata-strophic failure of a main feedwater pipe, which resulted in fatal injuries to four workers.
This event was reported in TE Information Notice (TIN)86-106, "Feedwater Line Break," on December 16, 1986; IN 86-106, Supplement 1, on February 13, 1987; and IN 86-106, Supplement 2, on March 18, 1987.
The licensee submitted Licensee Event Report t LER1 F6-020-00 on January 8, 1987; Revision 1, LER.86-620-n],
on January 14, 1987; and Revision 2, LER 86-020-02, on March 31, 1987.
A comprehensive report entitled "Surry Unit ? Reactor Trip and Feedwater Pipe Failure Report," was attached to the updated LEP, Revisions 1 and 2.
The findings of NRC's Augmented Inspection Team were issued on February 10, 1987, in IE Inspection Report Nos. 50-280/86-42 and 50-281/86-42.
Investigation of the accident and exjtmination of data by the licensee, NRC, and others led to the conclusion that failure of the piping was caused by erosion/corrosion of the carbon steel pipe wall.
Although erosion/corrosion pipe failures have occurred in other carbon steel systems, particularly in small diameter piping in two-phase systems and in water systems containing suspended solids, there have been few previously reported failures in large diameter systems containing high-purity water.
Consistent with general indus-try practice, the licensee did not have in place an inspection program for examining the thickness of the walls of feedwater and condensate piping.
Main feedwater systems, as uell as other power conversion systems, are impor-tant to safe operation.
Failures of active components in these systems, for example, valves or pumps, or of passive components such as piping, can result in undesirable challenges to plant safety systems required for safe shutdown and accident mitigation.
Failure of high-energy piping, such as feedwater
(:P707020018 ZA 6?oewtt) c
&UkC&
JI7bfP-// A7
MPCB 87-01 July 9, 1987 Page 2 of 3 system piping, can result in complex challenges to operating staff and the plant because of potential systems interactions of high-energy steam and water with other systems, such as electrical distribution, fire protection, and security systems.
All licensees have either explicitly or implicitly committed to maintain the functional capability of high-energy piping systems that are a part of the licensing basis for the facility.
An important part of this com-mitment is that piping will be maintained within allowable thickness values.
Actions Requested:
Within 60 days from the receipt of this bulletin, licensees are requested to provide the following information concerning their programs for monitoring the wall thickness of pipes in condensate, feedwater, steam, and connected high-energy piping systems, including all safety-related and non-safety-related piping systems fabricated of carbon steel:
- 1.
Identify the codes or standards to which the piping was designed and fabricated.
- 2.
Describe the scope and extent of your programs for ensuring that pipe wall thicknesses are not reduced below the minimum allowable thickness.
Include in the description the criteria that you have established for:
- a.
selecting points at which to make thickness measurements
- b.
determining how frequently to make thickness measurements
- c.
selecting the methods used to make thickness measurements
- d.
making replacement/repair decisions
- 3.
For liquid-phase systems, state specifically whether the following factors have been considered in establishing your criteria for selecting points at which to monitor piping thickness (Item 2a):
- a.
piping material (e.g.
chromium content)
- b.
piping configuration 'e.g., fittings less than 10 pipe diameters apartl
- c.
pH of water in the system (e.g., pH less than 10)
- d.
system temperature (e.g., between 190 and 5000 F0
- e.
fluid bulk velocity (e.g., greater than 10 ft/s)
- f.
oxygen content in the system (e.g., oxygen content less than 50 ppb)
- 4.
Chronologically list and sumnarize the results of all inspections that have been performed, which were specifically conducted for the purpose of identifying pipe wall thinning, whether or not pipe wall thinning was discovered, and any other inspections where pipe wall thinning was dis-covered even though that was not the purpose of that inspection.
- a.
Briefly describe the inspection program and indicate whether it was specifically intended to. measure wall thickness or whether wall thick-ness measurements were an incidental determination.
- b.
Describe what piping was examined and how (e.g., describe the inspec-tion Instrument(s), test method, reference thickness, locations examined, means for locating measurement point(s) in subsequent inspectionsO.
NRCB 01 July 9, 1987 Page 3 of 3
- c.
Report thickness measurement results and note those that were Identi-fied as unacceptable and why.
- d.
Describe actions already taken or planned for p4ping that has been found to have a nonconforming wall thickness.
If you have performed a failure analysis, include the results of that analysis.
Indicate whether the actions involve repair or replacement, including any change of materials.
- 5.
Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
The written report shall be submitted to the appropriate Regional Administrator under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954, as amended.
In addition, the original of the cover letter and a copy of the report shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for reproduction and distribution.
This request for information was approved by the Office of Management and Budget under blanket clearance number 3150-0011.
Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C. 20503.
NRC intends to summarize the information collected under this bulletin and study it to help determine if additional actions are required by the staff and/or industry.
The information will be analyzed and placed in the PDR.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate NRC regional office or the technical contacts listed below.
ýha r s.Rossi, D c&/i~
Divi ion of Operati n I Events Assessment Office of Nuclear Rdtor Regulation Technical Contacts:
Paul Wu, NRR (301) 492-8987 Conrad McCracken, NRR (301) 492-7042
Attachment:
List of Recently Issued Bulletins
Attachmnt nee 37-01 Jufly 9. lot?
11i 1ilt I n 0o.
86-04 86-03 56-02 86-01 115-03 85-02 65-01 LIST OF RECIETLY ISSUED IULLtTINS Da to Of Subject Issuance Defective Teletherapy Timer 10/29/86 that May Not Terminate Cose Potential Failure of Multiple 10/8/86 ECCS Pumps Due to Single Failure of Air-Operated Valve in Minimu flow Recirculation Line Static *0" Ring Differential 7/18/86 Pressure Switches Minimum Flow Logic Problems S/13/86 That Could Disable KHR PumPs Motor-Operated Valve Common 11/15/85 rode Failures During Plant Transients Due to Improper Switch Settings Uindervoltaoe Trip Attachments 11/5/85 of Westinghouse DO-SD Type Reactor Trip Breakers Steam Binding of Auxiliary 10/2/85S Feedwater Pumps Issued to All KSC licensees
.authorized to use cobalt-lO Uletherapy units All. facilities holding an OL or CP All power reactor facilities bolding en OL or CP All GE £SV facilities holding an OL or CP All power reactor facilities holding en DL or CP All power reactor facilities holdinq an %L or CP Nuclear power facilities and CPs listed In Attachment I for action; all other nuclear pever facilities for Information O. - Operating License CP - Construction Permit UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20556 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE. 1300 FIRST CLASS MAILF POSTAGE 6 FEES PAID USNhC WASH. D.C.
PERMIT No G47
NRCB 87-01 July 9, 1987 Page 3 of 3
- c.
Report thickness measurement results and note those that were identi-fied as unacceptable and why.
- d.
Describe actions already taken or planned for piping that has been found to have a nonconforming wall thickness.
If you have performed a failure analysis, include the results of that analysis.
Indicate whether the actions involve repair or replacement, including any change of materials.
- 5.
Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
The written report shall be submitted to the appropriate Regional Administrator under oath or affirmation under provisions of Section 18?a, Atomic Energy Act of 1954, as amended.
In addition, the original of the cover letter and a copy of the report shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for reproduction and distribution.
This request for information was approved by the Office of Management and Budget under blanket clearance number 3150-0011.
Comments on burden and duplication may be directed to the Office of Management and Budget, Peports Management, Room 3208, New Executive Office Building, Washington, D.C. 20503.
NRC intends to summarize the information collected under this bulletin and study it to help determine if additioral actions are required by the staff and/or industry.
The information will be analyzed and placed in the PDR.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate NRC regional office or the technical contacts listed below.
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts:
Paul Wu, NRR (301) 492-8987 Conrad McCracken, NRR (301) 492-7042
Attachment:
List of Recently Issued Bulletins
/
- SEE PREVIOUS CONCURRENCES D4 1 *.-NRR
- C/OGCB:DOEA:NPR CERo si CHBerlinger 01,
/E7 07/01/87
- ECEB:DEST:NRR *AC/ECEB:DEST:NRR
- EAD/DEST:NRR
'D7DEST:NRR *PPMB:ARM PWu CMcCracken t'Richardson LShao TechEd 06/29/87 06/29/87 06/29/87 06/30/87 06/29/87
IEB 87-XX June xx, 1987 Page 3 of 3
- c.
Report thickness measurement results and note those that were identi-fied as unacceptable and why.
- d.
Describe actions already taken or planned for piping that has been found to have a nonconforming wall thickness.
If you have performed a failure analysis, include the results of that analysis.
Indicate whether t0e actions involve repair or replacement, including any change of materials.
- 5.
Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
The written report shall be submitted to the appropriate Regional Administrator under oath or affirration under provisions of Section 182a, Atomic Energy Act of 1954, as amended.
In addition,.the original of the cover letter and a copy of the report shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for reproduction and distribution.
This request for information wasapproved by the Office of Management and Budget under blanket clearance number 3150-0011.
Comnents on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C. 20503.
NRC intends to summarize the information collected under this bulletin and study it to help determine if additional actions are required by the staff and/or industry.
The information will be analyzed and placed in the PDR.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate NRC regional office or the technical contact listed below.
Charles E. Rossi, Director Division of Operational Event Assessment Office of Nuclear Reactor Regulation Technical Contacts:
Paul Wu, NRR (301) 492-8987 Conrad McCracken, NRR (301) 492-7042 Attachments:
- 1. IE IN 86-106
- 2.
IE IN 86-106, Supplement I
- 3.
IE IN 86-106, Supplement 2
- 4. List of Recently Issued IE Bulletins
- SEE PREVIOUS CONCURRENCES
- ECEB:DEST:NRR *AC/ECEB:DEST:NRR PWu CMcCracken 06/29/87 06/29/87 D/DOEA:NRR CERossi 06/ /87
- D/DEST:NRR LShao 06/30/87
/
CB EA:NR CHBerl inger "I/r/*
Otr/ 1/87
- PPMB:ARM TechEd 06/29/87
- EAD/DEST:NRR JRichardson 06/29/87
IEB 87-XX June xx, 1987 Page 3 of 3
- c.
Report thickness measurement results and note those which were Identified as unacceptable and why.
- d. Describe actions already taken or planned for piping which has been found to have a nonconforming wall thickness.
If you have performed a failure analysis, include the results of that analysis.
Indicate whether the actions involve repair or replacement, including any change of materials.
- 5.
Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.
The written report shall be submitted to the appropriate Regional Administrator under oath or affirmation under provisions of Section 182a, Atomic Energy Act of 1954, as amended.
In addition, the original of the cover letter and a copy of the report shall be transmitted to the U.S. Nuclear Regulatory Commission, Document Control Desk, Washington, D.C. 20555 for reproduction and distribution.
This request for information was approved by the Office of Management and Budget under blanket clearance number 3150-0011.
Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management, Room 3208, New Executive Office Building, Washington, D.C. 20503.
NRC intends to summarize the information collected under this bulletin and study it to help determine if additional actions are required by the staff and/or industry.
The information will be analyzed and placed in the PDR.
If you have any questions about this matter, please contact the Regional Administrator of the appropriate NRC regional office or the technical contact listed below.
Charles E. Rossi, Director Division of Operational Event Assessment Office of Nuclear Reactor Regulation Technical Contacts:
Paul Wu, NRR (301) 492-8987
-Conrad McCracken, NRR (301) 492-7042 Attachments:
- 1. IE IN 86-106
- 2.
IE IN 86-106, Supplement 1
- 3.
IE IN 86-106, Supplement 2
- 4.
List of Recently Issued IE Bulletins
/IDOEA:NRR C/OGCB:DOEA:NRR CERossi CIEerlinger
!6/ 7 06/ /87 ECEB:DEST:NRR AC/*CEB:DEST:NRR EAD/DEST:
R 0/.RR PPMB:AR PWu CMcCracken JRichards LSh o TechE S0168/70 87 06/A /87 06ý0./87 0