ML19353A849
| ML19353A849 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/30/1989 |
| From: | Bates R VIKING SYSTEMS INTERNATIONAL |
| To: | NRC |
| Shared Package | |
| ML19353A850 | List: |
| References | |
| CON-NRC-03-87-028, CON-NRC-3-87-28 GL-88-01, GL-88-1, NUDOCS 8907030268 | |
| Download: ML19353A849 (50) | |
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TECHNICAL EVALUATION REPORT ON RESPONSE FROM e,
P NORTHEAST UTILITIES
'IO GENERIC LETTER 88-01 PERTAINING TO THE-
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MILLSTONE NUCLEAR POWER STATION, UNIT NO. 1 Published June, 1989 t
prepared by Robert C. Bates Armand Lakner Viking Systems International 2070 Wm. Pitt Way l-Pittsburgh, PA Prepared for:
U.S. Nuclear Regulatory Commission Washington, D. C. 20555 under 4
Contract No. NRC-03-87-028, Task Order 005 l-
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.e ABSTRACT This report contains an evaluation of the licensee (Northeast Utilities) submittal for Millstone Nuclear Power Station, Unit No. I which was.
submitted in response to the NRC Generic Letter 88-01 in which Northeast Utilities was requested to: (1) Furnish their current plans relating
.to piping replacement and other measures to mitigate IGSCC, inspection, repair, and leakage detection.
(2) Indicate whether they plan to follow the NRC Staff positions, or propose alternative measures. Northeast Utilities' plans are evaluated in Section 2 of this report in terms of compliance to NRC Staff positions. Section 3 contains an; evaluation of an alternative position concerning a change to the Technical Specification on ISI and an alternative position concerning leakage detection..
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SUMMARY
The Licensee, Northeast Utilities, submitted a response to the NRC' Generic Letter 88-01. Northeast Utilities' response pertaining to
.the austenitic stainless steel piping in the Millstone Nuclear Power Station, Unit No. 1 (a BWR nuclear power plant) was evaluated in terms I
of: (1) Their previous and planned actions to mitigate IGSCC to provide assurance-of continued long-term service.
(2) Their Inservice Inspection (ISI) Program.
(3) Their Technical Specifications pertaining to ISI and their plans to ensure that leakage detection will be in conformance with the NRC Staff position. (4) Their plans to notify the NRC of significant flaws identified (or changes in the condition of the welds previously known to be cracked) dur.ing inspection.
t Northeast Utilities endorses eleven of the 13 NRC Staff positions which are outlined in Generic Letter 88-01. They endorsed one with provisions (i.e., that on HWC because results of a pre-implementation test does not warrant its use), and they presented an alternative position on leakage detection.
Extensive programs of piping / weld replacement and other-mitigating actions have been conducted at Millstone, so half of the 410 welds are IGSCC Category A, C, or E welds. Of the remaining welds, all except 21 (eight of which are inaccessible for inspection) have been inspected.
i Additional replacement or repair is planned on an as-needed basis, and stress improvementj (using the Mechanical Stress Improvement Process)
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is planned for 22 nozzle safe-end welds. Plans for future inspections conform with NRC Staff positions on schedule and on methode and personnel.
Details o'f the plans for the next inspection were provided which confirm Northeast Utilities' plan to conform with the NRC Staff position.
Northeast Utilities presented an alternative position to the NRC Staff position requesting a change to the TS on ISI. They also presented an alternative position on leakage detection. These positions are evaluated in Section 3 of this report.
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CONTENTS ABSTRACT 1
SUMMARY
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- 1. INTRODUCTION 1
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- 2. EVALUATION OF RESPONSE IV GENERIC LETTER 88-01 2
2.1 Documents Evaluated 2
2.2 Review of Northeast Utilities' Responses to Staff Positions and Implementation of Those Positions 3
2.3. Northeast Utilities' Previous' Mitigating Actions, Classification of Welds,- and. Previous Inspection Program 4-2.3.1 Weld Classifications and Overview of Mitigating Actions and Inspections 4
2.3.2 IGSCC Category A Welds 4
2.3.3. Stress Improvement 8
2.3.4 Wald Overlays 9
2.3.5 Previous Inspection Programs 9
2.3.6 Evaluation of Previous Mitigating Actions and Previous Inspections 10 2.4 Current Pla'ns for Mitigating Actions 10 l -
2,4.1 Plans for Piping Replacement and Weld Overlays 11 2.4.2 Stress Improvement 11 2.4.3 Hydrogen Water Chemistry 12 l
2.4.4 Evaluation or Conformance to Staff Positions L-and Recommendation 13 l
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2.5 Plans for Future Inspections' 13 2.5.1 Summary of-Inspection Plans for 10 Year Cycle.....
13 2.5.2 Summary of Schedule for the 1989 Refueling Outage 15-2.5.3 Plans for Inaccessible Welds 15 2.5.4 Methods and Personnel 16 2.5.5 Sample Expansion 16 i
2.5.6 Evaluation and Recommendations 17' 2.6 Changes in the Technical Specification Concerning ISI 17-2.7 Confirmation of Leak' Detection
-in the Technical Specification 18 2.8 Plans for Notification of the NRC of Flaws 18 2.8.1 Evaluation and Recommendation 18
- 3. ALTERNATIVE POSITION 19 3.1 Alternative. Position Concerning ISI in the Technical Specification 19 3.1.1 Northeast Utilities' Position 19 3.1.2 Evaluation and Recommendation 19 3.2 Alternative Position Concerning Leakage Detection in the Technical Specification 20 3.2.1 Northeast Utilities' Position 20 3.2.2 Evaluation and Recommendation 23 iv
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- 1. INTRODUCTION I
i Intergranular stress corrosion cracking (IGSCC) near veldsents in i
Boiling k'ater Reactor (Bk'R) piping has been occurring for almost 20 o
years. Substantial efforts in research and development have been sponsored by the Bk'R Owners Group for IGSCC Research, and the results i
of this program, along with other related work by vendors, consulting firms and confirmatory research sponsored by the NRC, have permitted the development of NRC Staff positions regarding the IGSCC problems.
The techni:a1 basis for NRC Staff positions is detailed in Reference 1, and further background is provided in Reference 2.
The results of these research and development programs prompted the NRC to issue Generic 1.etter 88-01 (see Reference 3) requesting all licensees of Bk'R's and h'olders of construction permits to (1) Furnish their current plans relating to piping replacement, inspection, repair, and leakage detection.
(2) Indicate whether they (a) Plan to follow the staff pcsitions, or (b) Propose alternative mecuures.
Specifically, Generic 1etter 88-01 t.tated that an acceptable licensee response would include the following items:
(1) Current plans regarding pipe replacement and/or other measures taken or to be taken to mitigate IGSCC and provide assurance of continued long-term piping integrity and reliability.
(2) An inservice inspection (ISI) program to be implemented at the next refueling outage for austenitic stainless steel piping.
(3) A change to the Technical Specifications to include a statement 1
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in the section on ISI that the inservice inspection program for piping vill be in conformance with the staff positions on schedule, methods and personnel.
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(4) Confirmation of plans to ensure that the Technical Specification related to leakage detection will be in conformance with the Staff position on leak detection.
(5) Plans to notify the NRC, in accordance with 10CFR50.55a(o),
r of any flaws identified that do not meet IVB-3500 criteria of Section XI of the ASME Code for continued operation without evaluation, or a change found in the condition of the welds previously known to be cracked, and an evaluation of the flaws for continued operation and/or repair plans.
This report contains a technical evaluation of the response which Northeast Utilities (sometimes called NU in this report) submitted in response to the NRC Generic Letter 83-01 pertaining to the Millstone Nuclear Power Station, Unit No. 1 (hereafter called Millstone).
- 2. EVALUATION OF RESPONSE 'IV GENERIC LETTER 38-01 This evaluation consisted of a review of the response to NRC Generic
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Letter 88-01 of January 25, 1988 by Northeast Utilities pertaining L
to Millstone to determine if their performa ce and plans are in conformance with the NRC Staff positions or if proposed alternatives j
are acceptable. Proposed inspection schedulca and evaluation of l
Northeast Utilities' adherence to NRC recommendations to amend I
the Technical Specification were included in the review.
l 2.1 Documents Evaluated Review was conducted on the information pertaining to M111stona 2
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e provided by the Licensee in.the following documents.
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" Millstone Nuclear Power Station, Unit No. 1, Response to Generic letter 88-01 IGSCC in Austenitic Stainless Steel Piping, Docket No. 50-245, Northeast Utilities, P.O. Box 270, Hartford, Connecticut 06141-0270, July 27, 1988.
" Millstone Nuclear Power Station, Unit No. 1. Intergranular Stress Corrosion Cracking Inspection Plan for the 1989 Refueling Outage," Docket No. 50-245, Northeast Utilities, P.O. Box 270, Hartford, Connecticut 06141-0270, July 27, 1988.
" Millstone Nuclear Power Station, Unit No. 1, Response to Generic Letter 88-01 (Response to Request for Additional Information)," D,ocket No. 50-245, Northeast Utilities, P.O.
Box 270, Hartford, Connecticut 06141-0270, May 19, 1989 Hereafter, these documents will be referred to as the Northeast Utilities Submittals No. 1 No 2, and No. 3 respectively, and collectively as the Northeast Utilities Submittals.
2.2 Review of Northeast Utilities' Responses to Staff Positions and Implementation of Those Positions.
Generic Letter 88-01 outlines 13 NRC Staff positions pertaining I
to (1) materials, (2) processes, (3) water chemistry, (4) weld overlay, (5) partial replacement, (6) stress improvement of cracked weldments, (7) clamping devices, (8) crack evaluation and repair criteria, (9) inspection methods and personnel, (10) inspection schedules, (11) sample expansion, (12) leak detection, and (13) reporting requirements. Generic Letter 88-01 states that the licensee should indicate in their submittal whether they endorse these NRC Staff positions or propose alternative positions.
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Table 1 contains a summary of Northeast Utilities' responses.
Note that Northeast Utilities accepts eleven of the thirteen NRC Staff positions and applied provisions (or alternste proposals) to two (i.e., those on NWC and leakage detection).
2.3 Review of Previous Mitinating Actions Classification of Velds. and Previous Inspections 2.3.1 Weld Classifications and Overview of Mittynting Actions and Inspections Northeast Utilities included a copy'of their ISI plans for Millstone in Northeast Utilities Submittal No. 1.
Included in those plans were listings (by system, pipe diameter, and weld number) of the IGSCC classifications, pipe and weld compositions, previous mitigating actions, past inspection schedules, and inspections planned for the next refueling outage.
In addition, descriptions of their loreg range inspection plans (covering the current 10 year cycle) were also included.
Pertinent portions of this information are reproduced in Appendix A of this report. Susmaries for each piping diameter for the various piping systems are presented in Appendix B.
Overall summaries of mitigating actions and inspections schedules (including those conducted during the l
L last two refueling outages and scheduled for the next
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refueling outage) are presented in Tables 2 and 3, respectively.
2.3.2 IGSCC Category A Welds A total of 117 IGSCC Category A welds exist at Millstone.
The large number of welds of this category is the result 4
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Table 1 I
Summary of Northeast Utilities' Responses to Staff Positions NU Has/Will NU Accepts NRC Applied Consider for Staff Position Staff Position In Past Future Use
- 1. Materials yes yes yes
- 2. Processes yes yes yes no ")
yes ")
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- 3. Water Chemistry yes(*)
- 4. Weld Overlay yes yes yes
- 5. Partial Replacement yes res yes
- 6. Stress Improvement of Cracked Weldments yes yes yes
- 7. Clamping Devices yes no yes
- 8. Crack Evaluation and Repair Criteria yes yes yes
- 9. Inspection Method yes(b) yes(b) and Personnel yes
- 10. Inspection Schedule yes(b) y,,(b) y,,
- 11. Sample Expansion yes(b) y,,
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IC) yes(c)
- 12. Leak Detection yes yes
- 13. Reporting Requirements yes yes yes
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(a) IfWC pre-implementation test. preformed in 1987. Based on results of that test, a decision was made not to implement ilWC.
l (b) Credit is taken for 1985 and 1987 inspections which were performed per requirements of Generic Letter 88-01. Also Millstone contains some un-inspectable welds.
Northeast Utilities declined to change TS on ISI to include a statement that ISI will conform with the NRC Staff position.
(c) Northeast Utilities Submittal No. 2 states that they accept this item with provisions; however, they actually propose an alternate position. See text for discussion.
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Table 2 t-Summary of Mitigating Treatments Applied to Velds in Millstona IGSCC No. of Number of Welds with Indicated Treatment
- QLteg Velds SHT HSW CRC IHS1 0.L.
14 A(a) 117 8
19 22 0
0 0
l 3
0 C
76 0
0 0
76 0
0 D
184 0
0 0
0 0
0 E(D) 12 0
0 0
3 5
4 F
0 G (c) 13 0
0 0
0 0
0 3
G(}
8 0
0 0
0 0
0 2
Totals 410 8
19 22 79 5
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- Explanation of Abbreviations SHT - Soluti'on Heat Treatment I
HSW - Heat Sink Welding CRC - Corrosion Resistant Cladding IHSI - Induction Heating Stress Improvement 0.L. - Overlay I+0 - IHSI plus Overlay Notes:
(a)AlliGSCCCategoryAweldsthathavenotreceivedmitigating treatements are in corrosion resistant piping (i.e.,
the composition in compliance with ICSCC Category A as delineated in Generic Letter 88-01.
(b) The three IGSCC Category E welds that have been treated with IHSI contain flaws.
Four IGSCC Category E welds were overlayed after being treated with IHSI.
(c) Both the IGSCC Category G and G velds are IGSCC Category i
7 G welds, but G welds are accessible for inspection while i
G welds are not.
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i Table 3
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Summary of Previous Inspections (*) and Inspections Planned for 1989 at Millstone No. Inspected
% Inspected ICSCC No. in Past Schd
_Past Schd Required by Caten.
Caten.
85 87 1989 85 87 1989 Generic Letter 88-01 A
117 11 11 13 9
9 11 25% every 10 years (at least 12% in 6 years)
B 0
50% every 10 years (at least 25% in 6 years)
C(b) 76 9 76 16 12 100 21 All within the next 2 refueling cycles, then all every 10 years (at 50 % in 6 years)
D 184 62 122 92 34 66 50 All every 2 refueling cycles E(C) 12 9
4 11 75 33 91 50% next refueling cycle, then all every 2 refueling cycles F
0 All every refueling outage G (d) 13 0
0 13 0
0 100 All next refueling 1
outage C (d) 8 0
0 0
0 0
0 2
Notes:
(a) No flaws were reported except those in IGSCC Category E welds.
(b) All IGSCC Category C welds were inspected in 1987 so inspections for these welds will follow the second phase of the requirements, i.e., 100% re-inspection in 10 years.
(c) The one IGSCC Category E weld not to be inspected in 1989 was inspected in both 1985 and 1987 The other velds of this category were inspected in either 1985 or 1987 but not both.
l (d) IGSCC Category G welds are accessible and all will be inspected in 1989.
IGSCCbategoryG welds are inaccessible for inspection 2
j and will be continuously monitored (see text for discussion).
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l of extensive piping replacement, weld replacement, and other
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mitigating actions so that the IGSCC Category A welds include
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l the followings (a)' Resistant material welded to resistant material.
I (b) Resistant material welded to nonresistant material with Heat Sink Welding (HSW) or Corrosion Resistant Cladding (CRC) applied.
(c) Welds which join nonresistant material to nonresistant material which were welded using HSW or which were i
solution treated or clad (using CRC) after welding.
Confirmation of these statements is available from the weld histories, weld compositions, and piping compositions contained in Northeast Utilities Submittal No. 1.
It may be noted by reference to Table 2, Appendix A, or Appendix B that of the 117 IGSCC Category A welds: 8 were solution treated, 19 were welded using HSW, and 22 were clad with l
CRC. Although not shown in Table 2 or either of the I
appendices, the remaining 68 IGSCC Category A welds are composed of resistant materials.
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l 2.3.3 Stress Improvement Induction Heating Stress Improvement (IHSI) treatments were l
applied to a total of 83 welds. In each case, ultrasonic inspection was performed before and after the application of IHSI. Seventy-nine of these welds were found to be free l
of flaws, and inasmuch as the IHSI treatments were applied j'
after more than two years of service, these velds were classified as IGSCC Category C welds in keeping with the guidelines provided in NUREG 0313 Revision 2 and Generic I
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i Letter.88-01. Three of the welds that were treated with IHSI contain fisws. These welds are Classified as IGSCC Category E welds, although descriptions of the severity of the flaws was not provided. In addition, four of the IHSI-treated welds were later weld overlaid and are classified as IGSCC Category E welds.
2.3.4 Weld Overlays A total of 9 welds have been repaired with weld overlays (including the four previously mentioned welds that had been treated with IHSI) because they contained (or were suspected of containing) cracks. In all cases, the overleys were standard overlays which were acceptable per guidelines presented in NJIREG 0313. Revision 2.
Thus, these welds, are classified as IGSCC Category E welds.
2.3.5 Previous Inspection Programs e
Inspections have been performed at Millstone since 1973.
In 1985 a revised ISI program was implemented which incorporated examinations that were qualified under the NDE Coordination Plan agreed upon by the NRC, EPRI, and the BWR Owners Group. Inspections were performed in 1985 and 1987 that were qualified under that plan, and those inspections are credited by Northeast Utilities in the development of their response to Generic Letter 88-01. Inspections performed prior to 1985 are not credited.
As previously indicated, the inspection schedules for 1985 and 1987 (along with the inspection schedule planned for l-1989 to be discussed in a later section) are shown in Appendix l
A (on a weld-by-weld basis), Appendix B (summary on a system-by-system basis), and Table 3 (which summarizes the total 9
.O plant inspection schedules). As can be seen by referring to those tables, 18% of the IGSCC Category A welds and 100%
of the IGSCC Category C, D, and E welds were inspected in either 1985 or 1987. Only 21 (eight of which are inaccessible for inspectione) of the 410 welds at Millstone remain uninspected. Flaws were found or suspected in the 12 welds.
Nine of these flawed welds were repaired with weld overlays.
The other three flawed welds were mitigated with IHSI, but the severity of the flaws was not disclosed,
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I 2.3.6 Evaluation of Previous Mitigating Actions and Previous Inspections An extensive program has been conducted at Millstone so that mitigating actions in the form of piping / weld replacement.
HSW, SHT, CRC,'IHSI, and/or weld overlay repairs have been applied to half (205) of the 410 welds that fall within the scope of Generic Letter 88-01. An extensive ISI program has also been pursued at Millstone.
Since the inspection i
methods and personnel used during the 1985 and 1987 inspections were qualified under the NRC/EPRI/BWR coordination program, it is recommended that those inspections should be accepted for purposes of implementing the NRC Staff inspection guidelines.
2.4 Current Plans for Mitigating Actions I
The Millstone Countermeasures Program, according to the Northeast l
Utilities Submittals, is an aggressive program for the detection and mitigation of IGSCC which allows for the repair or replacement I
of degraded welds that cannot be justified for service, on a case by case basis. In addition, stress improvement treatments are planned, and implementation of Hydrogen Water Chemistry (HWC) is t'
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being evaluated. These plans are discussed below in greater detail.
2.4.1 Plans for Piping Replacement and
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Weld Overlays Northeast Utilities Submittal No. 1 contains the following t
statements:
" Pipe replacements will utilize Nuclear Grade stainless steel, (<0.035% carbon), an inventory of which is maintained at the Millstone site. Welding will be performed using heat sink welding or corrosion resistant cladding techniques. Weld filler materials for replacement velds will be low carbon Type 308L or 316L stainless steel, having a minimum delta ferrite of 8FN and a maximum of 17FN. For degraded welds that cannot 4
be feasibly replaced, weld overlay repairs will be performed using low carbon type 308L stainless steel weld wire. The Gas Tungsten Arc Welding process will be employed using automated equipment and techniques to every' extent possible."
"Whenever veld overlay repairs or partial replacements are performed, additional stresses are accounted for i
in the affected piping stress analysis, and in the fracture mechanics analyses of crack growth in cracked welds of the piping, as applicable."
2.4.2 Stress Improvement l
L Northeast Utilities Submittal No. 2 states that 22 nozzle l
L safe-end welds with Inconel 182 will be treated during the 1989 refueling outage with Mechanical Stress Improvement Process (MSIP). The nozzle welds to be treated are shown 11
4 in Table 4 of this report as reproduced from Attachment 1 of Northeast Utilities Submittal No. 2.
Table 4 Welds to be Treated with MSIP at Millstone
- Diameter, Number of Norrle/ System inches Nozzle Velds Head Instrument 9
1 Head Spray 9
1 Ilead Vent 6
1 Isolation Condenser 14 2
CRD Cap 5
1 Core Spray (2 nozzles, 10 4
l 2 welds in each)
Recirculation Inlet 12 10 Recirculation Outlet 28 2
l 2.4.3 Hydrogen Water Chemistry A Hydrogen Water Chemistry pre-implementation test was completed in the fall of 1987 The results of that test l
are being evaluated to determine whether HWC will be implemented in the future at Millstone.
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w 2.4.4 Evaluation of Conformance to Staff Positions j
and Recommendation i
Since (1) plans exist for replacement of piping / welds on an as needed basis, (2) plans exist for application of MSIP treatment to 22 welds, (3) extensive mitigating actions have already been applied at Millstone, (4) Hydrogen Water 1
Chemistry (if it is introduced) should further reduce the possibility of IGSCC at Millstone, and (5) an aggressive ISI program is being applied (as discussed in the next section of this report) Northeast Utilities' current plans concerning mitigating treatments are reasonable. Therefore, acceptance or Northeast Utilities' plans is recommended.
i 2.5 Plans for Future Inspections Northeast Utilities stated that an augmented inspection program will be conducted at Millstone which was constructed based on the NRC Statf position as delineated in Generic !Atter 88-01. That plan pertains to the current 10 year cycle, beginning with the 1985 and including the 1987 inspections previously described.
Both their overall plan for the 10 year cycle (which will include a minimum of 5 refueling outages) and the specific, weld-by-weld schedule for the 1989 refueling outage (descriptions of which are included in Northeast Utilities Submittal No. 1) are discussed in the following sections.
2.5.1 Summary of Inspection Plans for 10 year Cycle The following is a summary of inspection plans, based on information supplied in Northeast Utilities Submittal No.
1.
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-4.
The Northeast Utilities ISI program is computer based l
and includes listings of all welds within the scope of Generic Letter SS-01 and NUREG 0313, Revision 2.
For IGSOC Category A welds: The minimum number of welds to be examined during each refueling outage is 5% of the total and a minimum of 25% during the 10 year cycle (with at least 12% in 6 years).
)
For IGSCC Category C welds: Recall that 100% of the velds of this category were inspected (using methods and l
personnel qualified per NRC Staff guidelines) in 1987.
Beginning in 1989, a minimum of 20% of the total number of welds o,f this category will be inspected during each refueling outage. All of the welds will be inspected during 10 years, and at least 50% vill be inspected in t
6 years.
For IGSCC Category D welds: 100% of these weids will be examined every 2 refueling cycles (50% per refueling cycle).
For IGSCC Category E welds: 100% of these welds will be examined every 2 refueling cycles.
For IGSCC Category G welds: All of the welds of this category welds which are accessible for inspection will be inspected during the next refueling cycle.
Inaccessible welds are discussed in a later section.
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h 2.5.2 Sunnary of 7pjpection Schedule for the1989Rej[gt;1inaOutane It can be stren by reference to Appendix A Appendix B or
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Table 3 that the plans as presented in Northeast Utilities Submittal Kc. 1 and outlined in the previous section are being imple:ented starting with the 1989 refueling cycle.
In addition to the above, Northeast Utilities Submittal No.
2 contains the following statement pertaining to welds scheduled c,C MSIP treatments:
"A pre-MG1P ultrasonic test inspection will be performed on those velds that were not inspected to the upgraded 1985 EPRI NDE Center Qualification Program. The post-MSIP ultrasonic test inspection will be performed on all 22 nozr.les welds."
2.5.3 Plans for Ingecessible Welds Information provided in Northeast Utilities Submittal No.
1 pertaining to inaccessible welds is summarized below.
Millstonn contains eight inaccessible IGSOC Category G welds. These welds will be continuously monitored for,leaka.ge by the drywell sump monitoring system to restricted leakage limits; however, the leakage limits to be imposed and the effectiveness of this monitoring were not provided in Northeast Utilities Submittal No.
1.
The applicability of a local leak detection system utilizing scoustic emission is being evaluated for 5 of the inaccessible weldments (those that are < 10 inch diameter),, but they have not found a vendor's system that is totally reliable.
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I i-The above information was supplemented with the following statement in Northeast Utilities Submittal No. 2:
l 1
" Installation of an acoustic local leak detection system on the X-16B Core Spray piping penetration (a Category l
G weld as defined in NUREG-0313, Rev. 2).
The system will be used to collect background noise level data during Cycle 13. No plans beyond Cycle 13 have yet been made regarding this system."
i 2.5.4 Methods and Personnel Both the inspection methods and inspection personnel qualifications for inspection that have been conducted since 1985 as well as those that will be conducted in the future are qualified per guidelines presented in Generic Letter 88-01 and NUREG 0313 Revision 2, i.e., through the NRC/EPRI/
BWROG coordination plan.
2.5.5 Sample Expansion Northeast Utilities Submittal No. I contains plans for sample expansion in the augmented inspection program that vill conform to the NRC Staff position as delineated in Letter l
88-01. A summary of those plans follows.
For ICSCC Catencry A and C welds: If one or more welds are found to contain suspected cracks, then an additional 1-number of welds will be examined. The additional sample of welds vill be approximately equal to the original sample. Welds will be distributed by the same pipe size, system, and location parameters used for the selection of the original sample, unless it is determined that there is a technical reason to select a different l
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distribution. If suspected cracks are found in the udditional sample, then all welds of the same category shall be examined.
For IGSCC Catenorr D welds: Although not required by Generic Letter 88-01, the same provisions will be applied to IGSCC Category D welds as for IGSCC Category A and C welds.
For ICSCC Category E welds: Descriptions of plans for sample expansion for these welds precisely follow the write-up of requirements provided in Generic Letter 88-01.
2.5.6 Evaluation _and Recommendations _
The ISI program for accessible (inspectable) welds complies in every respect (schedule, methods and personnel qualification, and sample expansion) with the NRC Staff positions as delineated in Generic Letter 88-01 and NUREG 0313, Revision 2.-
'theref ore, acceptance of Northeast Utilities' ISI program for Millstone is recommended.
Northeast Utilities' plans for inaccessible welds, although partly in the developmental stage, follow guidelines presented in Generic Letter 88-01. Thus, acceptance of Northeast Utilities' plans for inaccessible welds is also recommended.
l 2.6 Changes in the Technical Specification Concerning ISI Northeast Utilities proposed an alternative position to the NRC Staff position concerning a change to the Technical Specification.
This alternative position is discussed in Section 3 of this report.
17 i
i 2.7_ Confirmation of Leak Detection in the o
Technical Specification i
Northeast Utilities proposed an alternative position to the NRC t
Staff position concerning leakage detection. This alternative i
position is discussed in Section 3 of this report.
i l'
2.8 Plans for Notification of the NRC of Flaws The Northeast Utilities' Submittal states that the NRC will be notified of'ilaws in accordance with the NRC Staff position as j
delineated in Generic Letter 88-01. Specifically:
" Examination results will be reported in the Inservice Inspection Outage Summary Report provided to the NRC within 90 days following completion of the scheduled refueling outage."
"A summary of inspection results of welds that do not meet the acceptance criteria of ASME Section XI I 4 3500 for continued operation without evaluation will be provided to l
.the NRC. This summary vill also provide information relative l
to any change found in the condition of welds previously known to be cracked. The evaluation of such flaws and/or repair l
plans performed or planned will be included in the subject report."
l 2.8.1 Evaluation and Recommendation Northeast Utilities' plans comply with the NRC Staff position, so it is recommended that the plans for reporting of flaws l-should be accepted.
1 18 l
l i
i O-
- 3. ALTERNATIVE POSITIONS a
3.1 Alternative Position Concernina ISI in the Technical Specification i
3.1.1 Northeast Util,ities' Position i
Northeast Utilities Submittal No. I contains the following statetents:
"The ICSCC Inspection Program provided in the attachment is consistent with the guidelines of NUREG-0313 Revision 2.
The program is controlled in accordance with our Nuclear Engineering and Operations Group procedures, and will be implemented in accordance with the same."
"In light of the above, NKE00 does not believe that a change to the Technical Specifications is warranted.
Furthermore, the computer based IGSOC Program presented i
herein can be readily updated to reflect revised NRC requirements and current program status, as required.
A new, updated inspection plan will also be developed for each succeeding refueling outage, and will be submitted to the NRC prior to the outage. NNE00 has historically submitted the IGSCC inspection plan to the NRC at least three months prior to each refueling outage, at the request of the NRC. This submittal process will be continued using the updated IGSCC Program described herein."
3.1.2 Evaluation and Recommendation l
Northeast Utilities' ISI program including the computer based system which can be readily updated is excellent, and the 19
.e continuance of this program is recommended. However, this does not adequately fulfill or substitute for the requirement specifically delineated in Generic latter 88-01 to change the Technical Specification to include a statement that the section on ISI will conform with the NRC Staff position on schedule, methods and personnel, and sample expansion. Thus, rejection of the NortTeast Utilities position is recommended, and Northeast Utilities should amend the Technical Specification to inchde the statement on ISI that is required by Generic Letter 88-01.
3.2 Alternative Position LeaknRe Detection in the i
Technical Specification o
3.2.1 Northeast Utilities' Position Northeast Utilities Submittal No. I contains the following statement:
"The staff position on leak detection, as defined in NUREG 0313 Revision 2, and Generic Letter 88-01, is incorporated in Technical Specifications 3.6.D, and in plant operating procedures. While Technical Specification l
4.6.D requires that reactor coolant leakage into the primary containment be checked and recorded at least l
once per' day, Surveillance Procedure No. SP 635.1,
):
' Reactor Coolant System Leakage Check,' requires the monitoring of reactor coolant leakage every four hours."
Northeast Utilities Submittal No. 3 contains additional information and clarification of their position:
" Surveillance Procedure No. 635.1 is controlled by the 20
l t
Technical Specifications: Section 6.8, page 6-16. This r
requires that all operating procedures be established, implemented and maintained in accordance with the 1
Technical Specification. Secondly, changes thereto shall be reviewed by the PORC/ SOP,C, as applicable, and approved l..
by the Unit Superintendent prior to implementation."
In addition, the information shown in Table 5 is contained in Northeast Utilities Submittal No. 3.
The following footnotes are applicable to that tables (a) " Millstone Unit No. 1 currently determines unidentified leakage into the drywell with the drywell floor drain sumps. This function is performed in t
accordance with Station Procedure SP 635.1."
"NNECO has previously addressed the issue of compliance with Regulatory Guide 1.45 in response to SEP Topic V-5: Reactor Coolant Pressure Boundary Leakage Detection. In doing so NNE00 established a Limiting Condition for Operation (LCO), consistent with the Standard Technical Specifications, based on the availability of existing instrumentation in calculating the rate of reactor coolant leakage from unidentified sources into the drywell.
Included in that amendment are changes to the provisions of t
the Technical Specifications pertaining to the definition of ' OPERABLE,' and reactor coolant system i
leakage monitors. The Staff accepted the above resolution and approved the subject amendment to the Standard Technical Specifications."
Note: Northeast Utilities then referred to the correspondence listed as references 4, 5, and 6 in l
21 1
1 r
L l;
Table 5 Licensee Positions on Leakage Detection Already TS will be Alternate Contained Changed Position 1
i Position in TS to Include Proposed no(*)
yes(8)
- 1. Conforms with Position C of no Regulatory Guide 1.45
- 2. Plant shutdown should be i
initiated when:
no(*)
yes(b)
(a) within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> no or less, an increase is indicated in the rate of unidentified leakage in excess of 2 gpm, or (b) the total unide'ntified leakage no(*)
yes(b) no attains a rate of 5 gpm.
no(a) y,,(c)
- 3. Leakage monitored at four hour no intervals or less.
- 4. Unidentified leakage includes all exCupt!
no(a) y,,(d)
(a) leakage into closed systems, no or no(a) y,,(d)
(b) leakage into the containment no atmosphere from sources that are located, do not interfere vith monitoring systems, or not from throughwall crack.
- 5. Provisions for shutdown within 24 yes(a) hours due to inoperable measurement l.
instruments in plants with Category l
D, E, F, or G velds.
Note: See text for footnotes (a) through (d).
l l
j.
22 1
i
f t
I Section 5 of this report.
i (b) " Millstone Unit No. 1 Station Procedure SP-635.1 requires surveillance of the drywell floor drain sumps every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. If the floor drain leak rate
[
is 2.5 gps, an orderly shutdown must commence, having the reactor in cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (as defined in Technical Specification 3.6.D)."
(c) " Station Procedure SP-635.1 requires surveillance every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."
(d) " Station Procedure SP-635.1 has provisions for determining leak rates of both unidentified and identified leakage."
3.2.2 Evaluation and Recommendation 7
The Millstone requirements for leakage detection are largely contained in the Station Operating Procedures rather than in the Technical Specification. However, this does not l.
adequately fulfill or substitute for the requirement specifically delineated in Generic Letter 88-01 to include leakage requirements in the Technical Specification. In i
addition, as may be seen by an examination of Table 5 and the footnotes to that table, the Millstone requirements do not completely satisfy the requirements delineated in Generic Letter 88-01. Thus, it is recommended that Northeast Utilities' position on leakage detection should be rejected.
It is further recommended that they should change their Technical Specification to reflect the leakage detection requirements listed in Generic Letter 88-01.
l' l
23
- 4. CONCLUSIONS AND RECOM(ENDATIONS i
Concerning the thirteen NRC Staff positions as delineated in Generic Letter 8S-01: Northeast Utilities endorsed eleven of the thirteen NRC Staff positions (i.e., those pertaining to materials, processes, weld I
overlay, partial replacement, stress improvement of cracked weldsents, clamping devices, crack evaluation and repair criteria, inspection methods and personnel, inspection schedule, sample expansion, and reporting requirements).. Based on the results of a pre-implementation.
test, Northeast Utilities decided not to implement Hydrogen Water Chemistry. Northeast Utilities presented an alternate position to the NRC Staff's position on leakage detection.
An extensive program has been applied to mitigate IGSCC at Millstone including piping / weld replacement, solution treating, heat sink welding, application of corrosion resistant cladding, application of induction heating stress improvement, and repair of welds using weld overlays.
As a result, half of the 410 welds have received some form of mitigating treatment. Of the remainder, 184 have been inspected using methods and personnel consistent with NRC Staff guidelines. Only 21 uninspected corrosion-susceptible welds remain. Eight of these are inaccessible for inspection.
Northeast Utilities plans piping replacement or weld overlays for mitigating degraded welds, on an as-needed case-by-case basis. In addition stress improvement treatments (using the MSIP process) will be performed on 22 ' nozzle safe-end welds during the 1989 refueling outage.
An inservice inspection program (ISI) has been developed for Millstone which complies with the requirements of Generic Letter 88-01 pertaining to schedule, methods and personnel, and plans for reporting flaws.
Inspections in 1985 and 1987 were conducted using methods and personnel that comply with NRC Staff requirements, so those inspections were 24
credited in the development of the plan to be implemented during the 1989 refueling outage. Detailed, weld-by-weld inspection schedules and descriptions of mitigating actions, veld histories and compositions h t th p n for ns e t 1 el s a 1
ne o r with NRC Staff positions. 1he Northeast Utilities position on sample expansion and reporting requirements also comply with NRC Sta2f positions.
Eight velds are inaccessible for inspection. These welds will be monitored using restricted leakage measurements. Acoustic emission monitoring of five of the welds (those less than 10 inches in diameter) i is under evaluation.
Installation of an acoustic local leak detection system on the S-16B Core Spray piping penetration is planned, and that system will be used to collect background noise level data.
Northeast Utilities declined to change the Technical Specification on ISI.
Rather they proposed to rely on their Inservice Inspection Program. Their ISI program is excellent, but such action was specifically rejected in Generic Letter 88-01.
Leakage requirements at Millstone are governed primarily by Surveillance Procedures rather than by the Technical Specification. This is unacceptable because the Surveillance Procedures do not carry the same weight as the Technical Specification. In addition, some differences L
in leakage requirements exist (some aspects of the Millstone requirements are less restrictive).
j As a result of this technical evaluation, the following recommendations l
are made.
(1) Acceptance of Northeast Utilities' ISI program including credit for 1985 and 1987 inspections, the schedule for the next refueling outage (scheduled for 1989), the plan for the 10 year cycle, plans for sample expansion, and their position 25
c' a
j on reporting of. flaws to the NRC.
(2) Acceptance of Northeast Utilities' plan for monitoring inaccessible welds 1
(3) Rejection of Northeast Utilities' position concerning changes ta the Technical Specification on ISI. It is further recommend that Northeast Utilities should amend their Technical Specification on ISI to include the required statement that 4
i the ISI program will conform to the NRC Staff position on schedule, methods and personnel, and sample expansion.
(4) Rejection of the Northeast Utilities position on leakage detection. Northeast Utilities should amend their Technical Specification on leakage detection to include the requirements listed in Generic Letter 8B-01.
(5) Acceptance of the remaining portions of Northeast Utilities Submittals.
I l
l l
l l
l 26
m
.l
- 5. REFERENCES 1.
" Technical report on Material Selection and Processing Guidelines for BVR Coolant Pressure Boundary Piping," KUREG 0313. Revision
- 2. U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, January, 1988.
F 2.
" Investigation and Evaluation of Stress-Corrosion Cracking in Piping I
of Light Water Reactor Plants," NUREG 0531, U. S. Nuclear Regulatory Commission February, 1979, 3.
"NRC Position on IGSCC in BVR Austenitic Stainless Steel Piping,"
Generic Letter 88-01, U.S. Nuc1 car Regulatory Commission January 25, 1988.
4 NRC letter to Mr. W. G. Counsil from James J. Shea, " MILLSTONE 1 IPSAR SECTIONS 4.91 4.10.16.1(5)," dated June 29, 1983 5.
NNEC0 letter to Mr. Dennis M. Crutchfield from W. G. Counsil,
" MILLSTONE 1 PROPOSED TECHNICAL SPECIFICATION CHANGE COOLANT LEAKAGE MONITORING," dated November 1, 1983.
6.
NRC letter to Mr. W. G. Counsil from Dennis M. Crutchfield,
" REDEFINITION OF THE WORK OPERABLE _ COOLANT LEAKAGE MONI'IVRING,"
dated May 23, 1984.
I l
27
2 :, s :..
Lq Appendix A c.
Mitigating Treatments, Previous Inspections, and
' ~'
Inspections Planned for 1989 for Welds in Millstone t
t r
I Inspections IGSCC
' Weld Dia.
Treatment Past Schd Caten System
- Number inch.
85 87 1989 A
LPCI CCBJ-6 16 X
X i
A LPCI CCBJ-9 16 X
X l
l A
-Core Spray CSAJ-l 10 A
Core Spray CSAJ-2 10 X-X
-A Core Spray CSAJ-3 10 X-A' Core Spray.
CSAJ-4 10 X
A Core Spray CSAJ-5 10 X
A Core Spray CSAJ-6 10 A.
Core Spray CSAJ-7
_10 X
l A_
Core Spray CSAJ-8 10 A
Care Spray CSAJ-9 10 A
Core Spray CSAJg10 10 X
A Core Spray CSBC-G-1A 10-X A
Core Spray CSBC-G-2A 10 X
i A
Core Spray CSBJ-1 10 X
A Core Spray CSBJ-2 10 X
A Core Spray CSIU-3 10 X
.f A
~CSBJ-4 10 i
A Core Spray CSBJ-5 10
.A Core Spray CSlu-6 10
~ ;
A Core Spray CSBJ-7 10 A
Core Spray CSBJ-8 10 i
A Core Spray CSBJ-9 10 A
Core Spray CSBJ-10 10 X
A Core Spray CSBJ-12A 10 X
A Core Spray CSIU-13A 10 X
X 1
See page A-2 for c'xplanation of abbreviations of systems I
n A-1 q
l a
a N ;.
i
. ;c.
+, n,
Appendix A (conL4nued) i4 Inspections
Treatment Past Schd
-Catec __pystem Number
. inch.
85 87 1989 A
RWCU-Supply CUAJ-l 8
X X
A RWCU-Supply CUAJ-2 8
X X
t A
RWCU-Supply CUAJ-7A 8
X X
A RWCU-Supply CUAJ-8A.
8 A
RWCU-Supply CUAJ-9A 8
A RWCU-Supply CUAJ-10A 8
A RWCU-Supply CUAJ-llA 8
A RWCU-Supply CUAJ-llB 8
X X
A RWCU-Supply CUAJ-14A 8
X F
A RWCU-Supply 'CUAJ-15A 8
.A RWCU-Supply CUAJ-16A 8
A RWCU-Supply CUAJ-17A 8
t
-A RWCU-Supply CUAJ-18A e
A RWCU-Supply CUAJ-19A 8
X X
A RWCU-Supply CUAJr198 8
A RWCU-Supply CUAJ'22A 8
A RWCU-Supply CUAJ-23A 8
.A RWCU-Supply CUAJ-24A 8
A RWCU-Supply CUAJ-25A 8
X A
RWCU-Return CUAJ-10 8
X
'A RWCU-Return CUAJ-11 8
X Explanation of Abbrevia'tions of Systems RPV' Reactor Pressure Vessel CRD Control Rod Drive Jet Pump RPV Jet Pump Instrumentation Head Vent RPV Head Vent Head Inst RPV Head Instrument Recire Reactor Recirculation RWCU-Supply. Reactor Water Clennup Supply RWCU-Return Reactor Water Cleanup Return Shut Cool Shutdown Cooling LPCI Low Pressure Coolant Injection
.lsoc-Supply Isolation Condenser Supply Isoc-Return Isolation Condenser Return 1
A-2
gW i
i.
Appendix A (continued)
Inspections I.
IGSCC k' eld Dia.
Treatment Past Schd Caten System Number inch.
85, 87 1989 A
Isoc-Supply ICAC-F-1A 16 X
X A
Isoc-Supply ICAC-F-3A 16 X
X A
I soc-Su ppl y ICAC-F-4A 16 A
Isoc-Supply' ICAC-F-5A' 16 A
_Isoc-Supply ICAC-F-6A 16 A
Isoc-Supply ICAC-F-7A 16
[
A Isoc-Supply ICAC-F-7B 16 X
A Isoc-Supply ICAJ-l 14 X
A Isoc-Supply ICAJ-3 14 X
A Isoc-Supply ICAJ-4 14 A
Isoc-Supply ICAJ-5 14 A
Isoc-Supply ICAJ-6 14 A
Isoc-Supply ICAJ-7 14 A
Isoc-Supply ICAJ-8.
14 A
Isoc-Supply ICAJ+9 14 A
Isoc-Supply ICAJ-10 14 A
Isoc-Supply ICAJ-11 14 A
Iso.-Supply ICAJ 14 X
[
A-Iso,-Lupply ICAJ-14 14 X
X A
Isoc-Supply ICAJ-15 14 X
A-Isoc-Supply ICAC-BF-1 12 X
A Isoc-Supply I CAC-BF-2 12 X
A Isoc-Supply ICAC-F-16A
'12 X
X A
Isoc-Supply ICAC-F-17 12 A
Isoc-Supply ICAC-F-18 12 A
Isoc-Supply ICAC-F-19 12 A
Isoc-Supply ICAC-F-21 12 X
A Isoc-Supply ICAC-F-21A 12 X
A Isoc-Supply ICAC-F-21B 12 X
A Isoc-Supply ICAC-F-22 A 12 A
Isoc-Supply,ICAC-F-23A 12 i
A Isoc-Supply ICAC-F-24A 12 A
Isoc-Supply ICAC-F-24B 12 A
Isoc-Supply ICAC-F-24C 12 X
A Isoc-Supply ICAC-F-25A 12 X
A Isoc-Supply ICAC-F-26 12 A
Isoc-Supply ICAC-F-27 12-A Isoc-Supply ICAC-F-28 12 A
Isoc-Supply ICAC-F-29 6
X A
Isoc-Supply I CAC-F-30 6
A Isoc-Supply ICAC-F-31 6
X l
A-3
pr 1
4 i.
=
Appendix A (continued)
L Inspections
-IGSCC
. Weld Dia.
Treatment Past Schd Catec System Number inch.
SHT llSW CRC lilSI 0.L.
85 87 1989 A'
Isoc-Return ICBJ-CAP 14 X
A ~
Isoc-Return ICBJ-8 10 X
X A
Isoc-Return ICBJ-9 10 A
Isoc-Return IChJ-10 10 A
I soc-Return - ICBJ-ll 10 X
A Isoc-Return ICBC-F-l l -
8 X
X A
Isoc-Return ICBC-F-12A 8
X A
Isoc-Return ICBC-F-14A 8
X I
A Isoc-Return ICBC-F-14B 8
X A
Jet Pump JPAF-1 A 5
A-Jet Pump-JPBF-1A 5
A Recirc RCAJ-9 28 A
Recirc RCBJ'9 28 A
Recirc' RHAJ-PRA 22 X
A Recire RMAJ-RRB 22 X
A Recire RMAJ-RRD 22 X
A Recirc RMAJ-RRE 22 X
A Recire RMAJ-RRF 22 X
A Recirc RMAJ-RRG 22 X
A Recirc RMAJ-RRJ 22 X
A Recirc RMAJ-RRK 22 A
Recire RCAJ-30 4
X X
A Recire RCAJ-32 4
X A
- Recirc RCBJ-32 4
X A
Recire RCBJ-34 4
X A
Shut Cool SCAJ-1 14 X
X A
Shut Cool
,SCAJ-2 14 X
A Shut Cool SCAJ-3 14 X
.A Shut Cool SCAJ-CUl 14 X
X A-4 l
p p-f App:ndix A (contin 3:d)
Treatment Past Schd Caten-Svstem Number inch.
85 87 1989
]
C LPCI CCAJ-6 16 X
X X C
Recire RCAJ-1A 28 X
.X X
C Recire RCAJ-2 28 X
X X
C Recirc RCAJ-3 28 X-X C
Recirc-RCAJ-4 28 X
X C-Recire RCAJ-5 28 X
X X C
Recire RCAJ-6 28 X
X X C
Recirc RCAJ-8 28 X
X X C
Recirc RCAJ-10 28 X
X C
Recirc RCAJ-11 28 X
X C
Recire RCAJ-12 28 X
X C
Recirc RCAJ 28 X
X C
Recire RCAJ 28 X
X-C Rectre RCAJ-15 28 X
X C
Recirc RCBJ 28 X
X C
Recirc RCBJ-1 A 28 X
X C
Recirc RCBJ-2.
28 X
X C-Recirc' RCBJc3 28
'X X X C-Recirc RCBJ-4 28 X
X X C
Recirc RCBJ-6 28 X
X X C
Recire RCBJ-7 28 X
X X
.C Recire RCBJ-8 28 X
X X C
Recirc RCAJ 28 X
X C
Recirc RCAJ-ll 28 X
X C
Recirc RCAJ-12 28 X
X C
Recirc RCAJ-13 28 X
X C
Recirc RCAJ-14 28 X
X C
Recire RCAJ-15 28 X
X C
Recirc RCBJ-16 28 X
X C-Recirc RMAJ-RRC 28 X
X X
C Recirc RMBJ-RRH 28 X
X X C
Recirc RMAJ-1 22 X
X X C
Recirc RMAJ-2 22 X
X C
Recirc
'RMAJ-3 22 X
X C
Recirc RMAJ-4 22 X
X X
C Recirc RMAJ-5 22 X
X C
Recirc RMBJ-2 22 X
X C
Recirc RMBJ-3 22 X
X C
Recirc RMBJ-4 22 X
X X C
Recirc RMBJ-5 22 X
X A-5
f$
h y. :e i
(
Appendix A (continued)
Inspections 1GSCC' Weld Dia.
Treatment Past Schd Caten System Number inch. SHT HSW CRC IHSI 0.L.
85.87 1989 C
Recirc RCAJ-SCl.
_16 X
X X
C Recire RCAJ-CCI 16 X
X i
C-Recire RRAJ-l 12 X
X C
Recirc RRAJ-2 12 X
X C
Recire RRAJ-3 12 X
X C
.Recirc RRIU-3 12 X
X C
-Recirc RRBJ-4 12 X
X C
Recirc RRCJ-l 12 X
X X
C Recirc RRCJ-2 12 X
X X
C Recire RRCJ-4 12 X
X X
1 C
Recirc-RRDJ-l 12 X
X C
Recirc RRDJ-2 12 X
X 1
C~
Recirc RRDJ-3 12 X
X C
Recire RRDJ64 12 X
X l
~C Recirc RREJ-l 12 X
X X C
Recirc RRFJ-2 12 X
X C
Recirc RRFJ-4 12 X
X C
Recirc RRFJ-2 12 X
X
{
C Recirc RRFJ-3 12 X
X X
C Recire RRFJ-4 12 X
X l
C Recirc RRGJ-l 12 X
X C
Recire RRGJ-2 12 X
X i
C Recire RRGJ-3 12 X
X C
Recirc RRGJ-4 12 X
X C
Recirc RRHJ-l 12 X
X l
C Recirc RRHJ-2 12 X
X X C
Recire RRHJ-3 12 X
X C
Recirc RRHJ-4 12 X
X X C
Recirc RRJJ-l 12 X
X C
Recirc RRJJ-2 12 X
X C
Recire
, RRJJ-3 12 X
X C
Recirc RRJJ-4 12 X
X C
Recirc RRKJ-l 12 X
X C
Recirc RRKJ-2 12 X
X C
Recirc RRKJ-3 12 X
X C
Recirc RRKJ-4 12 X
X X l
A-6 f
7- --
L.
v 4 i
_y Appendix A (continued)
.Dia.
Treatment-Past Schd Catec System Number inch.- SHT HSW CRC IHSI 0.L.
85 87 1989 D
LPCI CCAJ-2 18 X
X D
LPCI CCAJ-3 18 X
X
^
D LPCI CCAJ-4 18 X
X D
LPCI CCAJ-5 18 X
X D-LPCI CCAJ-6 18 X
X D
- Li'CI CCAJ-7 18 X
X D
LPCI CCAJ-8 18 X
X D
LPCI CCAJ-9 18 X
X-D LPCI
.CCAJ-12 18.
X X
D LPCI CCAJ-13 le-X X
D LPCI CCAJ-14 18 X
X D
LPCI CCAJ 18 X
X D
LPCI CCAJ-16 18 X
X D
LPCI CCAJ-17 18 X
X D
LPCI CCAJ-18 18 X
X D
LPCI CCAJs19 18
-X X
D LPCI CCAJ-20 18 X
X D,
LPCI CCAJ-21 18 X
X D
LPCI-CCBJ-l 18 X
X D
LPCI CCBJ-2 18 X
X f
D LPCI CCIU-3 18 X
X 1
'D LPCI CCBJ-4 18 X
X D
LPCI CCBJ-10 18 X
X D
LPCI CCBJ-ll 18 X
X i
D LPCI CCBJ-12 18 X
X D
LPCI CCBJ-13 18 X
X i
D LPCI CCIU-14 18 X
X i
D LPCI CCBJ-15 18 X
X' I
D LPCI CCIU-16 18 X
X D
LPCI CCBJ 18 X
X l
D LPCI CCBJ-18 18 X
X a
D LPCI
,CCBJ-19 18 X
X i
D LPCI CCBJ-20 18 X
X D-LPCI CCAJ-10 16 X
X L
D LPCI CCAJ-Il 16 X
X D
LPCI CCBJ-5 16 X
X i
l l
l l
A-7 1
I
b-9-
P t
Appendix A (continued)
[
Inspections-IGSCC Weld Dia.
Treatment Pa st Schd Catec System Number inch.
SHT HSW CRC 11151 O.L.
85 87 1989 JD Core Spray CSAC-G-1 10
-X
'D.
Core Spray CSAC-G-2 10 X
D' Core Spray CSAC-G-3 10 X-D Core Spray.
CSAJ-13 10 X
D Corc Spray CSAJ-14 10 X
D Core Spray CSAJ-15 10 X
D
' Core Spray CSAJ-16' 10 X
D
' Core Spray CSBC-G-2 10-X X D.
Core Spray CSBJ-13
= 10 X' X y
D Core Spray CSBJ-14 10 X
X D
Core Spray CSBJ-15 10 X
X D
Core Spray CSBJ-16 10 X
X 1
P f
T A-8
W:
.,...a.
h
[.
+
L i Appendix A (continued)
Inspections IGSCC -
- Weld.
Dia.
Treatment Past Schd Caten Spstem Number inch.
SIIT }{SW CRC IllSI 0.L.
85 87 1989 D
RWCU-Supply CUA-2 10 X
j D
RWCU-Supply CUA-3 10 X
i D_
RWCU-Supply _ CUA-4 10 X
D RWCU-Supply CUA-5 10 X
D
~ RWCU-Supply CUA-6 10 X
l D
RWCU-Supply CUA-8 10 X
D RWCU-Supply CUA-ll 10 X
D RWCV-Supply CUA-12 10 X
D RWCU-Supply CUA-13 10 X
D RbCU-Supply CUA-14 10 X
i D-RWCU-Supply' CUA-15 10 X
i D
RWCU-Supply CUA-16 10 X
{
D RWCU-Supply CUA-17 10 X
D.
RWCU-Supply' CUA-18 10 X-
-l D
RWCU-Supply CUA-19 10
~X j
D RWCU-Supply -CUA-20 10 X
D RWCU-Supply -CUA-21 10 X
D RWCU-Supply CUA-22 10 X
D~
RWCU-Supply CUA-23
-10 X
j j
D RWCU-Supply CUA-24 10 X
i D
RWCU-Supply CUA 10 X
l D
RWCU-Supply CUA-26 10 X
D RWCU-Supply CUA-1 8
X
-l D
RWCU-Supply CUA-9 8
X i
D RWCU-Supply CUA-10 8
X D.
RWCU-Supply CUA-27 8
X j
D RWCU-Supply CUA-28 8
X
}
D RWCU-Supply CUA-29 8
X D
RWCU-Supply CUA 8 X
D RWCU-Supply CUA-30A 8
X
)
D RWCU-Supply CUA-31 8
X D
RWCU-Supply,CUA-32 8
X D
RWCU-Supply CUAJ-3 8
X i
D RWCU-Supply CUAJ-4 8
X X
D-RWCU-Supply CUAJ-5 8
X X
l D-RWCU-Supply CUAJ-6 8
X X
D RWCU-Supply CUAJ-7 8
X X
D RWCU-Supply CUAJ-12 8
X D
RWCU-Supply CUAJ-13 8
D X
RWCU-Supply CUAJ-14 8
X A-9
~
p 4 ;,:.3 y,
t'r Appendix A-(continued) r Inspections 1GSCC' Weld Dia.
Treatment Past Schd Caten System-Number inch.
85 87'1989 n
D-RWCU-Return CUS-1 8
X D
RWCU-Return CUB-2 8
X D
RWCU-Return CUB-3 8
X D
RWCU-Return CUB-4 8
X D
RWCU-Return CUB-5 8
X D
RWCU-Return CUB-6 8
X
-D RWCU-Return CUB-7 8
X D
RWCU-Return. CUB-8 8
X D
RWCU-Return CUB-9 8
X D-RWCU-Return CUB-10 8
X D
RWCU-Return-CUB-Il 8
X D-RWCU-Return CUB-12' 8
X D
RWCU-Return CUB-13 8
X D
.RWCU-Return CUBJ-2 8
X X D
RWCU-Return CUBJ-3
-8 X X D
RWCU-Return CUBJ64 8
X X
'D RWCU-Return CUBJ-5 8
X X D
RWCU-Return' CUBJ 8 X X D.
RWCU-Return CUBJ-7 8
X D
RWCU-Return CUBJ-8 8
X D
RWCU-Return CUBJ-9 8
X D
RWCU-Return CUBJ-12 8
X D
RWCU-Return CUBJ-13 8
X D
RWCU-Return CUBJ-14 8
X D
RWCU-Return CUBJ-15 8
X D.
RWCU-Return CUBJ-16 8
X D
RWCU-Return CUBJ-17 8
X D
RWCU-Return CUBJ 8 X
X D
RWCU-Return CUBJ-19 8
X X
D Head Inst HIBF-1 9
X i
D Head Spr HIBF-1 9
X 5
lI A-10
n i'
~
g;; d, y s
9, 40'
'a Appendix A (continued)
Inspections IGSCC Weld-Dia.
Treatment Past Schd-Caten System Number inch.- SHT HSW CRC IHSI 0,L, 85 87 1989-D
-Recirc RCBF-1 28 X
D Recire RCBF-ICI 14 X X
'D Recire RRCF.I 12 X
X t
D Recirc RRDF 1 12 X
D Recire RRE '-1 12 X
X D
Recirc RRFF-1 12 X
X D
Recirc RRG-1 12 X
'X-D Recirc RC4J-PB1 4
X X
D Recirc RC/,J-PB2 4
X X
D Recirc.
RClJ-PB1-4 X
X D-Recire-RJJ-PB2 4
X X
D Shut Cool SCAFt2 14 X
D Shut Cool SOAJ-4 14 X
D Isoc-Supply ICAC-F-2 16 X X D
Isoc-Supply ICAC-F-8 16 X
X D.
Isoc-Supply ICAC-F-9 16 X X D
Isoc-Supply ICAC-F-10 16 X X D
Isoc-Supol)
ICAC-F-11 16 X
X.
D Isoc-Su ply LICAC-F-20 16 X X D
Isoc-Supply ICAC-F-1 14 X X D
Isoc-Supply ICBF-1 14 X
D
- soc-Supply ICAC-F-12 12 X
X D
Isoc-Supply 'ICAC-F-12A 12 X
X D
Isoc-Supply ICAC-F-14 12 X
X D
Isoc-Supply ICAC-F-15 12 X
X D
Isoc-Supply, ICAC-F-16 12 X
X A-11 i
p.
g
.:q s-;c.,
4-9~-_
<, - 1 Appendix A (continued)
Treatment Past Schd
'Caten System' Number inch.
85 87 1989 D
Isoc-Return ICBC-F-1.
10 X'
D Isoc-Return ICBC-F-2 10 X-
'D Isoc-Return ICBC-F-3 10 X
D Isoc-Return ICBC-F-4 10 X
D Isoc-Return ICBC-F 10 X
t D.-
Isoc-Return ICBC-F-6 10 X-D Isoc-Return -ICBC-F-7 10 -
X-D Isoc-Return ICBC-F-8 10 X
D Isoc-Return ICBC-F-9 10 X X D'
Isoc-Return ICBC-F-10 10 X X D
Isoc-Return ICBC-F-21 10 XX D
Isoc-Return ICBJ-l 10-X X D
Isoc-Return ICBJ-2 10 X X D
Isoc-Return ICBJ-3 10 X X D
Isoc-Return ICBJ-4 10 -
X X D
Isoc-Return ICBJ25 10 X
X D
Isoc-Return ICBJ 10 X
X D
Isoc-Return ICBJ-7 10 X
X D
Isoc-Return ICBJ-12 10' X
D lsoc-Return ICBJ-13 10 X
D Isoc-Return ICBJ-14
-10 X-D Isoc-Return ICBC-F-12 8~
X D
Isoc-Return ICBC-F-13 8
X D-Isoc-Return ICBC-F-15 8
X X D'
Isoc-Return ICBC-F-16 8
X X D
Isoc-Return ICBC-F-17 8
X X D
Isoc-Return ICBC-F-18 8
X X D
Isoc-Return ICBC-F-19 8
X X D
Isoc-Return ICBC-F-20 8
X X D
Isoc-Return ICBC-F-22 8
X X
- D Isoc-Return ICBC-F-22A 8
X X D
Isoc-Return JCBC-F-23 8
X X D
Isoc-Return ICBC-F-24 8
X D
Isoc-Return ICBC-F-25 8
X D
Isoc-Return ICBC-F-26 8
X D
Isoc-Return ICBC-F-27 8
X D
Isoc-Return ICBC-F-28 8
X D
Isoc-Return ICBC-F-29 8
X D
lsoc-Return ICBC-F-30 8
X A-12
p,
f5J
',6 - ' (;
,3, c.
Appendix A (continued)
- . g-Inspections ICSCC-Weld Dia.
Treatment Past Schd-l Cates System Number inch.
85 87 1989 E.
Isoc-Supply ICAC-F-3 16 X-X~
X E
Isoc-Supply ' ICAC-F-13 12 X
X X
E Recirc RCAJ-1(I) 28-X X
X E
Recire.
RCAJ-7(f)~
28' F.
X' X II)
I; Recirc RCBJ-5 28 X
X-X li E
Recire RMBJ-l 22 X
X X X E
Recirc RRAJ-4 12 X
X X
E Recirc RRBJ-l 12 X
X X
X j
E Recire RRBJ-2 12 X
X X
X i
1; Recirc RRCJ-3 12 X
X X
X i
E Recirc-RR f'J-3 12 X
X X
E Recirc
-RRFJ-3 12-X X
X 4
l Note: (f) on weld number indicates weld is flawed.
I i
l-l i
l-I i
1 1
l 4
l A-13 l
- - -.
- s '.r.
+
Appendix'A (continued) g
..' < 4 - e Inspections 1GSCC Weld Dia.
Treatment Past Schd Caten System Number inch.
SHT HSW CRC IHS1 0.L.
85 87 1989
-G
'CRD CRDF-1 5
X-3 G.
Core. Spray CSAF-1 10 X
3 G
Core Spray CSAF-2 10 X
3 G
Core Spray CSBF-1 10 X
G;j Core Spray CSBF-2 10 X
G licad ' Ven t ilI AF-1 6
X 3
G Isoc-Supply ICAF-1 14 X
3 G)-
Recirc RCAF-1 28 X
G Recirc RRAF-1 12 X
1 Cf Recirc RRBF-1 12 X
t G
Recirc RRilF-1 12 X
3 G
Recirc RRJF-1 12 X
I G
Rectre RRKFr,1 12 X
l
.i i
Appendix A (continued) i Inspections IGSCC Weld Dia.
Treatment Past Schd i
Catee Svstem Number inch. SHT llSW CRC lilSI 0.L.
85 87 1989 G,
Isoc-Supply (A)X-10A 14 G;
RWCU-Supply (A)X-14
'8 G'
Core Spray (A)X-16A 10 Gl-LPCI (A)X-43' 18 G;
Isoc-Return (B)X-llB 10 C;
RWCU-Return (B)X-15 8
i G;
-(B)X-16B 10 l
G; LPCI (B)X-45 18 A-14
p 9: 44.. v
+-
-4 g
.o
.,'o l
Appendix B-
, System-by-System Summary of Mitigating Treatments, Previous Inspections, P"
and Inspections Planned for-1989 for Welds in Millstone Number of Welds with No.-Inspect.
~IGSCC Dia.
No. of Indicated Treatment *-
Past Schd Catee System Inch Welds -
SHT HSW CRC IHSI 0.L. I+0 85 J87 1989 A-LPCI 16 2
2 2
A
' Core' Spray 10 24 4
2 1
6 3
A RWCU-Supply 8
19
,5 1
2 2
2 A
'RWCU-Return 8
2 2
A' Iso-Supply 16' 7
2 1
2 14
'13 3
1 2
12 18-4 3
1 1
6 3
2 A
Iso-Return 14 1
1 10 4
2 1
8 4
2 2
1 A
Jet Pump 5
2 A
Recirc 28 2
22 8
8 4
4 4
1
~A Shut Co'l.
14 4
2 2
2
!=
o Total ICSCC Categ A Welds 117 8 19.22 0
0 0
11 11 13 l
Explanation of Abbreviations SHT - Solution Heat Treatment HSW - Heat Sink Welding CRC - Corrosion Resistant Clodding o
L IHSI - Induction Heating Stress Improvement l'
O.L. - Overlay j.
1+0 - OHSI plus 0.L.
L B-1 l
c
p y,. q g., g t
p
- ,t f*:
Appendix B (continued)
Number of Welds with No. Inspect.
.ICSCC-Dia.
No. of Indicated Treatment Past Schd Catec System Inch Welds. SHT HSW CRC IHSI 0.L. I+0 85 87 1989 C-LPCI 16 1
~
1-1
'l C
Recirc 28 30 30 3 30.
9 22 9
9 1
9 2
16-2 2
1 2
12 M
34 34 4
Total'IGSCC Cates C Welds 76 0
,0 0 76 0
0 9 76
.16 Mumber of_ Welds with
_No. Inspect.
IGSCC Dia.
No. of Indicated Treatment Past Schd Catec System Inch Welds SHT HSW CRC IHSI O.L. I+0 85 87' 1989 D
LPCI 18 f.33 33 33 16 3
3 3
D' Core Spray 10 12 3
9 5
D' RWCU-Supply 10 22 22
.8 18 4 14 4
D RWCU-Return 8
29 2 27 7
i D'
Head Vent 9
2 2
and Inst D
Recirc 28 1
'l 14 1
1 1
12 5
4 1
4 4
4 4-4 D
Shut Cool 14-2 2
D Isoc-Supply 16 6
'2 5
6 14 2
I 2
1 12 5
4 5
D Isoc-Retur.,
10 21 3 18 10 8
18 18 9
Total IGSCC Categ D Welds 184 0
0 0
0 0
0 62 122 92 i
l l-B-2 L
(L "d;
2 9 w a-
. IP
' Appendix B (continued)
IGSCC Dia.
No. of.
Number of Welds with No. Inspect.
Indicated Treatment Past
-Schd Caten
-System Inch Welds SHT HSW CRC IHSI 0.L. I+0 85 87, 1989 E '-
Isoc-Supply _
16 1
I 1
1 12 1
1 1
1 E
Recirc 28 3
3 1
2 3
22 1
1 1
1 12 6
3-3 6
. 6
_ Total ICSCC Categ E Welds 12 0
0 0
3 5
4 9
4' 11 Number of Welds with No. 7nspect.
ICSCC Dia.
No. of Indicated Treatment Past Schd Caten System Inch Welds FHT HSW CRC IHSI O.l.,
140 85-87 1989.
G CRD-5' 1
3 1
G Core Spray.
4 3
10 4
G Heal Vent 6
1 3
1
-i G
Isoc-Supply 14 1
3 1
G-
-Recirc 28 1
3 1
12
,_S.
5 Total ICSCC Categ G Welds 13 0
0 0
0 0
0 0
0 13 3
Number of Welds with No. Inspect.
IGSCC Dia.
No. of Indicated Treatment Past Schd i
Caten System
I+O 85 87 1989 l
0 0
0 0
0 0
0 0
2 B-3
- - - - -