ML20151D206
| ML20151D206 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/18/1988 |
| From: | Eury L CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| GL-88-01, GL-88-1, NLS-88-160, NUDOCS 8807250010 | |
| Download: ML20151D206 (54) | |
Text
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+h carenne power a uent company P. O. Box 1551 + Raleegh, N. C. 27602
'JUL 181988 LYNN W. EURY senior vice President SERIAL: NLS 160 Operatons Support United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-o2 RESPONSE TO GENERIC LETTER 88-01 AND IGSCC INSPECTION PIANS - BSEE 1 REFUELING OUTAGE 6 Gentlemen:
Generic Letter 88-01, dated January 25, ~ 1988, c,utlined the new NRC Staff positions regarding intergranular stress corrosion cracking (IGSCC) in boiling water reactor (BWR) austenitic stainless steel piping. The technical basis for these positions is outlined in NUREG-0313, Revision 2.
Generic Letter 88-01 requested that BWR licensees respond a; to whether they intend to follow the Staff positions or propose alternative measures.
The information submitted herein contains Carolina Power & Light Company's (CP&L's) current plans concerning piping replacement, inspection, repair, and leakage detection as outlined in Generic Letter 88-01 for the Brunswick Steam Electric Plant (BSEP), Units 1 'and 2.
In addition 'o the response to Generic Letter 88-01, CP&L is also submitting ics plans for IGSCC inspections at BSEP-1 during Refueling Outage 6.
By letter dated May 19, 1987, CP&L commiteed to submit these plans at least three months prior to 'he start of the m e refueling outage. Refueling Outage 6 is current.ly scheduled to be. gin on November 12, 1988. The inf,.,rmation submitted herein for BSEP-1 de;teribes the plans for inspection, mitigative actions, and/or modificatien of aerv 4.c sensitive stainless steel piping as defined in NUREG '.M 3, Revision 2.
The information provided in this letter has been divided into five categories, each described in corresponding enclosures:
(1)
Backcround - A brief review of the measures taken at BSEP to detect, repair and/or mitigate IGSCC in austenitic stainless steel piping.
(2)
Susceptible Weld Population A summary of the susceptible weld population at BSEP as defined by NUREG-0313, Revision 2.
1 (3)
Es_sponse to Generic Letter 88 01 - An outlice'of CP&L's' positions as s
to the specific items requiring response in the Generic Letter.
(4)
BSEP-1 Inspection Plans for Refueline Outage 6 Inspection and 1
mitigative actions planned at BSEP-1 during Refueling Outage 6.
1 (
8807250010 880718 PDR ADOCK 05000324 P
s PDC
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Docunsnt Control Dask NLS-88-160 / Page 2 (5)
Summarv - A discussion of the bases used to formulate CP&L plans concerning the control of ICSCC in the future. includes the tables referenced in Enclosures 1 through 5. includes draft Technical Specification Pages.
Based upon the information provided in the enclosures listed-above, Carolina Power & Light Company believes that its current. plans for IGSCC inspection, mitigation, repair, and leakage detection meet or exceed the guidelines set forth in Generic Letter 88-01 and NUREG-0313, Revision 2.
Please refer any questions regarding this submittal to Mr, Stephen D.
Floyd at (919) 836-6901.
Yours very truly,
!4 L. W. Eu BAB/bab(\\cor\\igsccpl)
Enclosures:
===1.
Background===
2.
Susceptible Weld Population 3.
Response to Generic Letter 88-01 4
BSEP-1 Inspection Plans for Refueling Outage 6 5.
Summary 6.
. Tables
. 7 # Draft Technical Specification Pages L. W. Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.
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b ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES'DPR-71 & DPR-62 IGSCC INSPECTION PLANS BACKGROUND Numerous measures have been taken or will be taken to control and/or mitigate ICSCC at.both BSEP-1 and BSEP-2, These measures include, but are not limited to, the following:
(1)
Partial replacement of susceptible piping system with carbon steel material or resistant stainless steel materials.
(2)
Stress improvement of selected weldments, using both the Induction Heating Stress: Improvement Process (IHSI) and Mechanical Stress.
Improvement Process (MSIP).
(3)
Weld overlay reinforcement to repair flaws detected in reactor recirculation system welds.
(4)
Installation of a hydrogen water chemistry control system (HWC) which is currently in progress on BSEP-2 (to be' completed in 1988) and scheduled for BSEP-1 in 1989, El-1
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I ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 IGSCC INSPECTION PIANS SUSCEPTIBLE WELD POPULATION BSEP-1 and BSEP-2 have five systems which contain welds made of austenitic stainless steel, four inches or larger in nominal diameter, and contain reactor coolant at a temperature above 200 F.
These are the reactor recirculation system, the residual heat removal (RHR) system, the reactor water cleanup (RWCU) system, the core spray system, and the jet pump instrumentation portion of the nuclear boiler system.
The residual heat removal system welds (RHR, Ell) have been listed with the reactor recirculation welds in the attached tables.
A summary listing of the susceptible welds on each unit is provided in Table 1.
The following is a brief description of the susceptible weld population on each unit.
BSEP-1 Following completion of Refueling Outage 5 in 1987, the susceptible weld population on BSEP-1, based on Generic Letter 84-11, consisted of 108 welds.
Subsequent to issuance of NUREG 0313, Revision 2, in January 1988, CP&L conducted a review of service sensitive welds based on the new position redefining veld susceptibility.
Based upon this review, the BSEP-1 susceptible weld population now consists of 266 welds, 70 of which are Class 1 welds not covered under Generic Letter 84-11, and 88 are in the non-code classified, non-safety related portion of the RWCU system.
BSEP-2 The susceptible weld population of BSEP-2 consists of 180 welds, as described in the CP&L submittal of March 25, 1988, NLS-88-073, "BSEP-2 Refuel 7 Inspection Results." Based upon a review similar to that performed on BSEP-1 after issuance of NUREG 0313, Revision 2, the BSEP-2 susceptible weld population now consists of 264 welds of which 85 are in the non-code classified, non-safety related portion of the RWCU system.
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ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 IGSCC INSPECTION PLANS RESPONSE TO GENERIC LETTER 88-01 In Generic Letter 88-01, the NRC requested that each BWR licensee furnish a response to five specific items involving IGSCC concerns.
The following items are addressed below: (1) Current Plans; (2) In-Service Inspection (ISI) Program; (3) Technical Specifications; (4) Leakage Detection; and (5)
Notification Policy.
(1)
CURRENT PLANS CP&L's current plans regarding pipe replacement and/or measures taken or to be taken to mitigate IGSCC and provide assurance of continued long-term piping integrity and reliability are discussed below. A synopsis of this discussion is included as Table 2.
l Measures Taken at BSEP-1 Prior to initial plant start up in March 1977, the reactor recirculation 4" discharge valve bypass lines were replaced using 304L (modified for strength) stainless steel material.
In 1979, the 10" stainless steel core spray piping was replaced with carbon steel material and the core spray safe-ends were replaced with F316L stainless steel materia?
During Refueling Outage 4 in 1985, IHSI was performed on 79 welds in the reactor recirculation system. During the same outage, the Class 1 RWCU system piping from the residual heat removal tie-in to the outside containment isolation valve and the Phase I RWCU system piping from the outside containment isolation valve to the regenerative heat exchanger were replaced using conforn.ing 316 stainless steel material.
Conforming stainless steel material, as used in the context of this submittal, refers to materials considered resistant to sensitization and IGSCC as defined in NUREG-0313, Revision 2.
IGSCC inspections p*rformed since 1983 have detected flaws in 37 welos of the reactor recirculetion system.
Thirty-six of these have been repaired by weld overlays and meet the standard design requirements of NUREG-0313, Revision 2.
One weld contains a flaw first detected during Refueling Outage 4.
IHSI was performed on this weld and it was re-examined during Refueling Outage 5.
The flaw exhibited essentially no change in its characteristics. Analyses performed showed that this weld was acceptable for continued service without repair.
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Measures To Be Taken at BSEP-1 During the upcoming Refueling Outage 6, CP&L plans for mitigation and/or control of IGSCC are as follows:
(a)
Inspections: Ultrasonic Testing of selected welds will be performed based on the inspection schedules listed in Table 1 of NUREG 0313 Revision 2.
(b)
Replacement: The remaining susceptible portions of the RWCU system will be replaced using a. low carbon wrought austenitic stainless steel material, per NUREG 0313, Revision 2.
(c)
MSIP: Safe-end to nozzle welds in the reactor recirculation,-
core spray, and jet pump instrumentation systems will receive MSIP treatment.
(d)
Repairs:
Based upon the results of examinations, welds found to be unacceptable for continued operation wi.1.1 be repaired by either a weld overlay or a pipelock.
(e)
Hydrogen Water Chemistry:
Installation of the hydrogen water chemistry system is scheduled during this period.
Plans for the years following Refueling Outage 6 will follow the established guidelines presently being employed at BSEP, subject to future developments in IGSCC research.
Measures Taken at BSEP-2 The reactor recirculation 4" discharge valve bypass lines were replaced using 304L (modified for strength) stainless steel' material in 1976 during the first outage following initial plant startup in November 1975.
The 10" stainless steel core spray lines were replaced with carbon steel materisi in 1977, and the core spray safe-ends were replaced with inconel 600 material in 1979.
During Refueling Outage 6 in 1986, IHSI was performed on 65 welds on the reactor recirculation system.
During the sale outage, the Class 1 i
and Phase 1 portions of the RUCU system were al*; replaced using conforming 316 stainless steel material.
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'IGSCC inspections'have detected flaws'in 43 welds of the reactor recirculation system.
Forty-one,of these welds have been. repaired by weld. overlay; four of which are designed overlays.and 37 are standard overlays.
Fifteen inconel 182 butter safe end to nozzle welds received MSIP applications during the recently completed Refueling.
Outage 7.
Two of these welds, the 28" reactor recirculation' system suction nozzle to safe-end welds, had small axial indications.which were detected during Refueling Outage 6.
These welds were re-examined during Refueling Outage 7 and an analysis was performed which
= indicated these welds were acceptable for continued service without repair.
Hydrogen water chemistry installation was started during Refueling Outage 7 and is currently scheduled to be completed in 1988.
Measures To be Taken at BSEP-2 CP&L's current plans for controlling and/or mitigating IGSCC include the fc11owing measures:
(a)
Inspections: Ultrasonic examination of selected' welds will be performed based on the inspection schedule listed in Table 1 of NUREG-0313, Revision 2.
(b)
Replacement: The remaining susceptible. portions of the RWCU system will be replaced using a low carbon wrought austenitic stainless steel material, per NUREG-0313, Revision 2.
(c)
Repairs:
Based upon the results of examinations, welds found to be unacceptable for continued operation will be repaired by either a weld overlay or a pipelock.
As with BSEP-1, future plans will follow the established guidelines presently being employed at BSEP, subject to future developments in IGSCC research, i
(2)
IN-SERVICE INSPECTION (ISI) PROGRAM CP6L has classified the "Service Sensitive" welds at both BSEP units into the seven categories of weldment conditions. Table 1 provides a summary of the selds contained in each of these categories. Tables 3 and 4 provide a complete listing for BSEP-1 and BSEP 2, respectively, of each weld along with mitigation and/or repair and inspection information.
Categories A and D have been subdivided in these listings to distinguish between the varying measures and types of inspections performed during past outages. The basis used in forming these specific sub-categories is discussed in the following sections.
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.ga;?qtry A Welds This category has been subdivided into three parts based on the veldment conditions.Categacy A selds consist mainly of the solution annealed welds and those made of resistant material which have been inspected since September 1985 when adoption of the upgraded NDE Coordination Plan was agreed upon by NRC, EPRI and BWROG.
Category A* welds are made of resistant material but have not been examined since September 1985.
Ct.tegory A** welds consist of the welds in the portion of the RWCU piping system which were replaced with resistant material, but have never been ultrasonically examined.
These welds, and several others replaced prior to these, were in non-code, non-safety related portions of the RWCU system and vere outside of the ASME Section XI boundaries.
Category D Welds The two sub-categories in this listing follow the same general characteristics as for Categories A and A* only differing in that they are composed of non-resistant material and have not been stress improved.
Those welda listed as Category D have been inspected since September 1985, while Category D* identifies those welds inspected prior to that date.
Weld 2-RWCU-R10A on BSEP-2 was inspected during Refueling Ourage 6 but inspection was performed under a separate program by others not related to the GE inspections.
In determining the specific ISI program to be implemented during the next refueling outages under the scope of Generic Letter 88-01, CP&L has formulated the following criteria and plans in relation to the inspection scope, schedules, methods, personnel, and sample expansion.
Inspection Scope The scope of inspections to be performed in future outages will be based on the requirements of Section 5 of NUREG-0313, Revision 2 and Table 1 of both Generic Letter 88-01 and NUREG-0313, Revision 2.
It was necessary to consider two areas not specifically sddressed in Generic Letter 88-01 or NUREG-0313, Revision 2 when establishing the inspection scope.
Criteria have not been established for baseline or pre-service examinations of (1) non-code, non safety related welds replaced with resistant material but never inspected and (2) those welds scheduled to be replaced with resistant material.
The re fore,
CP6L intends to perform inspections sa follows; E3 4
e (a)
For existing welds of resistant material not previously inspected due to code classification,' inspections will be
_ performed in accordance with the requirements set forth in Table 1 of NUREG-0313, Revision 2.
Twenty-five percent of these welds will be inspected every ten years.
(b)
For welds which will be. replaced in future outages, inspections will also be performed in accordance with the requirements set forth in Table 1 of NUREG-0313, Revision.2.
The 25% to be inspected over the ten year interval will be selected using criteria established for all IGSCC examinations prior to or j
during installation. These selected welds will receive a pre--
service UT to establish a baseline. Once the baseline is established, the ten year inspection schedule will be formulated to re-examine these welds.
These guidelines are based on the fact that these welds are contained
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in systems which have been classified as non-safety related and.are now composed of conforming material which is considered resistant to IGSCC. Additionally, the number of inspections proposed-is sufficient to assure that the structural integrity and reliability of the piping is maintained.
The criteria used for selection of welds to be examined will be the same as that used during.the recently completed refueling outage on BSEP-2 with the additional requirement (d), below.
The criteria are as follows:
(a)
The sample size of each category will be determined based on Section 5.0 and Table 1 of NUREG 0313, Revision 2.
(b)
A representative sample from each IGSCC category to ba examined will be based upon a review of susceptibility of-welds as determined from previous inspections.
(c)
Welds receiving mitigation and weld overlay repairs being upgraded or entering multiple fuel cycles of service will receive higher consideration.
(d)
Welds required to be examined under the ASME Code-Section XI schedule, as established for the second interval, will be considered for IGSCC inspection at the same time, if no other velds have a higher examination priority.
i (e)
ALARA l
Inspecticn Schedules The Staff positions as to the extent and frequency of inspections for the various categories of weldments will be followed in preparing future inspection schedules.
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Insoection Methods and Personnel
. Ultrasonic examinations will continue.to be performed employing both equipment and personnel qualified in accordance with the most current NRC/EPRI/BWROG coordination plan.
Samole Exoansion At the present time, CP&L plans co adhere to the provisions set forth in the Staff positions for flaws detected and determined to be caused by ICSCC. However, flaws initiated or caused by other mechanisms will be evaluated at that time as to determining the need for additional examinations within the provisions of Section XI of the ASME Code.
(3)
TECHNICAL SPECIFICATIONS Generic Letter 88-01 provides guidance for a revision to the Technical Specification Surveillance Requirements to include a statement that the ISI program for piping covered by the scope of Generic Letter 88-01 will be in conformance with the Staff positions.
Preparation of the documentation to affect this change in the Technical Specifications for both BSEP units is presently being performed. to this letter provides a preliminary draft of the proposed changes.
Submittal of these changes is contingent on concurrente by the NRC Staff with the response provided in this letter. This will ensure that CP&L will be in conformance with the Staff positions as presented in Generic Letter 88-01 and NUREG 0313, Revision 2.
(4)
LEAKAGE DETECTION Generic Letter 88 01 requests confirmation of CP&L's plans to ensure that BSEP Technical Specifications relating to leakage detection will be in conformance with the Staff positions included in the Generic Letter.
Currently, the BSEP Technical Specifications require that plant shutdown be initiated for inspection and corrective action when any leakage detection indicates, within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an increase in unidentified leakage in excess of 2 gpm, or when total unidentified leakage attains a rate of 5 gpm as averaged over any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.
Additionally, CP&L has committed via correspondence to the Staff to the following items:
(1)
For sump level monitoring systems with fixed measurement-interval methods, the level shall be monitored at 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> intervals or less.
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(2)
At least one of the leakage measurement instruments associated with each sump shall be operable and the outage time for inoperable instruments shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, an orderly 1
shutdown will be immediately initiated.
Based upon the above requirements and commitments, CP&L actions pertaining to leakage detection are in conformance with the Staff's positions outlined in Generic Letter 88-01.
(5)
NOTIFICATION PLANS Plans to notify the NRC of inspection results, evaluations, and actions to be taken regarding ICSCC related flaws will continue as they are presently formulated.
Inspection plans will be submitted three months prior to the start of a refueling outage on either BSEP-1 or SSEP-2.
Flaws or changes found in the condition of welds which do not meet ASME Code i
Section XI criteria will be reported in a Licensee Event Report (LER) within
)
30 days, if applicable, or through direct contact with the Staff in cases where a significant indication is detected as was done during the recently completed Refueling Outage 7 on BSEP-2 for the flaw found in the 12" reactor recirculation nozzle.
The results of specific inspections and the scope of mitigation and/or repairs which are performed during the refueling outages will be submitted to the Staif prior to startup of the unit.
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ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324 OPERATING LICENSES DPR-71 6 DPR-62 IGSCC INSPECTION PLANS BSEP-1 INSPECTION PLANS. REFUELING OUTAGE 6 The scope of mitigative actions and inspections during the upcoming BSEP-1 Refueling Outage 6 which is currently scheduled to begin on November 12, 1988 has been divided into four categories: (1) NUREG-0313, Revision 2, Inspections; (2) Mechanical Stress Improvement Process; (3) RWCU Piping Replacement; and (4) Hydrogen Water Chemistry Implementation.
Each category is discussed below.
(1)
NUREG-0313 Revision 2 Inspections The BSEP-1 Refueling Outage 6 inspection programs will includa ultrasonic testing of the following:
Category A Welds Table 5-1 provides a listing of the 16 welds which will be inspected during Refueling Outage 6.
Catecory B and F Welds BSEP-1 has no welds in these categories.
Category C Welds Table 5-2 provides a listing of the welds in this classification which have been selected for inspection during the Refueling Outage 6.
Category D Welds This category contains mainly the inconel butter nozzle welds and safe-end to thermal sleeve crevice welds. Table 5-3 provides a listing of the welds to be inspected during Refueling Outage 6.
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Categorv E Welds There are currently 36 standard weld _ overlay repairs on BSEP-1 of which all were inspected during Refueling Outage 5.
A total'of 18 welds, including 9 of.the 10 in service the longest, will be examined during Refueling Outage 6.
These welds are-listed in e
Table 5 4.
The remaining weld in this category, 28A8, has an existing analyzed flaw mitigated by IHSI.
This weld will be inspected during Refueling Outage 6.
Category G Welds Table 5-5 lists the two jet pump instrumentation safe-end to penetration seal welds which will be inspected during Refueling Outage 6.
Personnel performing IGSCC inspections will be qualified in accordance with the EPRI/BWROG/NRC coordination plan'.
(2) Mechanical Stress Imorovement Process (MSIP)
MSIP will be performed on selected inconel 182 butter welds of reactor pressure vessel nozzles.
Industry accepted methods of the O'Donnell and Associates Inc. patented process will be used.
The welds will be ultrasonically inspected before and after MSIP.
(3) RUCU Piping Reolacement The remaining 4" susceptible portions of the RWCU system will be replaced using conforming 316 stainless steel material.
(4) Hydrozen Water Chemistry Installation of a hydrogen water chemistry control system will be performed during Refueling Outage 6.
Design and installation will be the same as that currently being installed on BSEP-2.
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ENCLOSURE'5 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50-325 6 50-324 OPERATING: LICENSES DPR-71 & DPR-62 IGSCC INSPECTION PLANS
SUMMARY
As shown in this letter, CP&L has. maintained a strong comaitment to
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ensure that piping systems subject'to IGSCC are reliable _and retain their original integrity.
Constant updating of methods used to detect,.
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mitigate, and repair such as replacement with resistant material, state--
of-the-art inspections, weld overlay reinforcements, IHSI and MSIP applications, etc, are consistent with this-philosophy.
Installation of hydrogen water chemistry control systems and other related controls reflect a commitment to ensure continued safe operations of both BSEP-1 and BSEP-2 in the future.
In' summary, the plans presented in this letter provido the following facts:
l (1)
Plans regarding pipe replacement and/or measures taken or to be_
taken to mitigate IGSCC on both BSEP units provide assurance of continued long term piping integrity and reliability.
(2)
The ISI programs being implemented during the next refueling outages (Refueling Outage 6 for BSEP-1 and Refueling Outage 8-for BSEP-2) for austenitic stainless steel _ piping covered under the scope of Generic Letter 88-01 conform to Staff positions, j
(3)
Changes to the Technical Specifications on both BSEP units relating to ISI surveillance requirements are in the process of preparation, will conform with the Staff positions as defined in Generic Latter 88-01, and vill be submitted for review following Staff concurrence with the response provided in this letter.
(4)
Current BSEP plant requirements are in conformance with the Staff position relating to leakage detection.
(5)
Notification plans, as presented in this letter, provide for proper transmittal of information to the Staff on matters relating to IGSCC which would affect continued operation of the BSEP units.
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4 ENCLOSURE 6 BRUNSWICK STEAM ELECTRIC PIANT, UNITS 1 AND 2 NRC DOCKETS 50-325 6 50-324 OPERATING LICENSES DPR-71 6 DPR-62 ICSCC INSPECTION PIANS TABLES i
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LIST OF TABLES Table 1 Summary of Susceptible Welds Table 2 IGSCC Mitigation Measures Table 3 BSEP 1 IGSCC Susceptible Welds Table 4 BSEP-2 IGSCC Susceptible Welds Table 5 Inspection Limitations Table 5-1 Category A Welds To Be Inspected - BSEP-1 Refuel 6 Outage Table 5-2 Category C Welds To Be Inspected - BSEP-1 Refuel 6 Outage Table 5-3 Category D Welds To Be Inspected - BSEP-1 Refuel 6 Outage Table 5-4 Category E Welds To Be Inspected - BSEP-1 Refuel 6 Outage Table 5-5 Category G Welds To Be Inspected - BSEP-1 Refuel 6 Outage E6-2
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~~A B _ E '2 NtS i so IGSCC MiTIGATIO N MEASURES BSEPI BSEP 2 REACTOR RECIRC. '
. REPLACED 4 BY-PASS LINES
, REPL ACED 4"BY-PASS LINES SYS.
PRIOR TO IN ITI AL OPERATION.
IST OU TAGE.
. WELD OVERLAYS APPLIED
. WELD OVERLAYS APPLIED ON 36 WELDMENTS.
ON 41 WELDMENTS.
IHSl APPLIED DURING RF'6 TA KEN l H SI APPLIED DURING RF 4
+
TO 79 'WELDMENTS.
TO 65 WELDMENTS.
MSI P APPLICATION SCHED-
- MSIP APPLIED DURING RF ^ 7 TO BE TAKEN ULED FOR 12 WELDMENTS TO 1i WELD MENTS,
DU RI NG RF"6.
- HWC CURRENTLY BEING HWC SCHEDULED TO BE INSTALLED - SCHEDU L ED INSTALLED DURING RF 6, FOR COMPLETION 1988.
COMPLETION CURRENTLY SCHEDULED IN 1989, t
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TA 31 E 2 (CONra)
r RWCU SYSTEM REPLACED 6"CLASS 1 REPLACED 6
CLASSI PORTION DURING RF'4.
PORTION DURING RF " 6 0 'NON-REPLACED 4 + 6" NON -
REPLAJ5D 4 6
TAKEN SAFETY RELATED (PHASE I)
SAFETY RELATED (PHASE I)
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_ NUCLEAR BOILER SYSTEM (JPl) lN 1 -NOZZL E B32 -l REACTOR RECIRCULATION SYSTEM i
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37 APERTURE A PLANNED l
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ENCILSURE 7 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 6 50 324 OPERATING LICENSES DPR 71 & DPR 62 IGSCC INSPECTION PIANS DRAFT TECHNICAL SPECIFICATION PAGES
(BSEP-1-127)
APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillange Requirements shall be applicable during the OPERATIONAL CONDITIONS or other states specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a.
A maximum allowable extension not to exceed 25% of the surveillance
- interval, b.
A total maximum combined interval time for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.
4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification.
Surveillance requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection snd testing of ASME Code Class 1, 2, & 3 components shall be applicable as follows:
l Inservice inspection of ASME Code Class 1, 2, and 3. components and a.
inservice testing of ASME Code Class 1, 2, and 3 p'uinp7aIG valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commissior. pursuant to 10 CFR 50, Section 50.55a(g)
(6) (i).
I)ReFF BRUNSWICK - UNIT 1 3/4 G-2 Amendment No.
(BSEP-1-127) 3/4.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)-
b.
Surveillance intervals spec led in Section XI of the ASME Boiler and Pressure Vessel Ccde and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and l
Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing 17 service terminology for inservice inspection and testing j
inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterl or every 3 months At least once per 92 days S err' --
, or every 6 months At least once per 184 days y or annually At least once per 366 days l
l c.
The pro-isions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing j
activities.
d.
Pertormance of the sbove inservice inspection and testing activities shall be in addition to other specified Surveillance Requiremet.ts.
e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical i
Specification.
f.
The Inservice Inspectior Program for_pi, ping. identified in NRC Ceneric Letter 88-01 shall be formed in accordance with the Staff positions on schedule,
.thods, and personnel and sample expansion-included in this letter.
DRAFF B9UNSWICK - UNIT 1 3/4 0-3 Amendment No.
(BSEP-2-134)
APPLICABILITY SURVE!LLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL CONDITIONS or other stares specih ed for individual Limiting conditions for Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:
a.
A maximum allowable extension not to exceed 25% of the surveillance i
- interval, b.
A total maximum combined interval time for any 3 consecutive surveillance intervals noe to exceed 3.25 times the specified surveillance interval.
4.03.
Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for Operation and associated ACTION statements unless otherwise required by the specification. Surveillance requirements do not have to be performed on inoperable equipment.
4.04 Entry into an OPERATIONAL CONDITION or other specified applicable state shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the apclicable surveillance interval or as otherwise specified.
4.05 Surveillance Requirements for inservice inspection and testing of ASME i
Code Class 1, 2, and 3 components shall be applicable as follows:
Inserv.:e inspection of ASME Code Class 1, 2, and 3 components and a.
inservice testing of ASME Code Class 1, 2, and 3 pumps and valves
- s. tall be performed in accorcance with Section XI of the ASME Boiler and Pressare Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has beer.
granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)
(6) (i).
DRAFT BRUNSWICK - UNIT 2 3/4 0-2 Amendment No.
(BSEP-2-134) 3/t.0 APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued) b.
Surveillance intervals specified in Sece. ion XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing inspection and testing activities activitier Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least oncc per 366 days r
c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for perfo ming inservice inspection and testing activities.
d.
Performance of the above inservice inspection and testing activ! ties sha'l be in addition to other specified Surveillance Requirements.
e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
f.
The Inservice Inspection Program for piping identified in NRC Ceaaric Lettur 88-01 shall be performed in accordance with the Staff pos'.tions on schedule, metnods, and personnel ar.d sample exp nsion included in this generic letter.
DRBfT BRUNSWICK - UNIT 2 3/4 0-3 Amendment No.
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