ML20237D664
| ML20237D664 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/20/1998 |
| From: | BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML20237D642 | List: |
| References | |
| NUDOCS 9808270119 | |
| Download: ML20237D664 (85) | |
Text
E Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01
' THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PLAN FOR THE PILGRIM NUCLEAR POWER STATION l
TABLE OF CONTENTS SECTION DESCRIPTION PAGE Revision Summary Sheet iv 1.0 Introduction and Plan Description 1-1 l
1.1 Overview 1-1 1.2 Basis ofInservice Inspertion Plan 1-1 i
l 1.3 System Classification 1-2 1.4 Augmented Insenice Inspection Requirements 1-3 2.0 Inservice Inspection Program Drawings 2-1 2.1 Inservice Inspection Boundary Drawings 2-1 2.2 Piping Isometric Drawings 2-3
~~
3.0 ASME Section XI Insenice Inspection Tables 3-1 l
4.0 Alternative Requirements to ASME Section XI,1989 Edition 4-1 4.1 Adoption of Code Cases 4-1 4.2 Use of Subsequent Editions of ASME Section XI 4-3 4.3 Inservice Inspection Relief Request Index 4-4 4.4 Insenice Inspection Relief Requests 4-6 5.0 NRC Correspondence 5-1 iii
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9808270119 980820 PDR ADOCK 05000293 G
Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PLAN FOR THE PILGRIM NUCLEAR POWER STATION REVISION
SUMMARY
SHEET SECTION EFFECTIVE PAGE(S)
REVISION DATE 1.0 1-1 0
7/1/95 1.1 1-1 0
7/1/95 1.2 1-1 to 1-2 Amendment 98-01 4/15/98 1.3 1-2 to 1-3 0
7/1/95 1.4 1-3 0
7/1/95 2.0 2-1 0
7/1/95 2.1 2-1 to 2-2 0
7/1/95 2.2 2-3 to 2-7 Amendment 98-01 4/15/98 3.0 3-1 to 3-47 Amendment 98-01 4/15/98 4.0 4-1 0
7/1/95 4.1 4-1 to 4-3 0
7/l/95 4.2 4-3 0
7/1/95 4.3 4-4 to 4-5 0
7/1/95 4.4 Reference Section 4.3 for Revision Status of Relief Requests 5.0 5-1 Amendment 98-01 4/15/98
$Y
y Pilgrim Station 3rd Interval i
Inservice Inspection Plan Program Amendment 98-01 SECTION
1.0 INTRODUCTION
AND PLAN DESCRIPTION l
1.1 Overview
-1.1.1 This Inservice Inspection Plan outlines the requirements for the inspection of Class 1,2, and 3 pressure retaining w, pats and their supports at Pilgrim Nuclear Power Station.
1.1.2 This Inservice Inspection Plan will be effective from July 1,1995, through and including June 30, 2005, which represents the Third Ten-Year Interval for the
. Pilgrim Nuclear Power Station.
i 1.1.3
'Ihe key features of this plan are the Introduction and Plan Description, Relief Requests, and Summary Tables. The details of the Inservice Inspection Program are addressed in other documents that are available at Pilgrim Station. These documents include, but are not limited to, inservice inspection boundary drawmgs, piping isometric drawmgs, a wig,rst database listing of each weld, valve, support, etc., and h-
- supportmg implementation of the Inservice Inspection Program 1.2 Basis of Inservice I==aaeda= Plan l
1.2.1 - This Inservice Inspection Plan was developed in accordance with the requirements delineated in the January 1,1994 issue of 10 CFR 50.55a, and the 1989 Edition of l
the American Society of Mechanical Engmeers (ASME) Boiler and Pressure Velsel Code,Section XI, Subsections IWA, IWB, IWC, IWD, and IWF, for Inspection Program B. Accordingly, this Inservice Inspection Plan provides the detads necessary for performmg the inservice inspection of the Pilgrim Class 1, 2, i
j and 3 pressure retammg M-vi;= = = and supports. The requirements of ASME l
XI, Subsection IWE,1992 Edition and AM=h, are applicable to Pilgrim l.
Nuclear Power Station but are not required for submittal. The IWE program plan l
is not included in this program amendment.
1.2.2 The following ASME Section XI,1989 Edition Subsections, Articles, or Paragraphs are not included or addressed in this Inservice Inspection Plan.
1.2.2.1 The pump and valve testing requirements of Subsections IWP and IWV l are not included in this Inservice Inspection Plan. The rules ofIWP and IWV are addressed in a separate submittal to the NRC staff.
L l-1
,( '
Pilgrim StItion 3rd Interval -
l Inservice Inspection Plan Program Amendment 98-01 1.2.2.2 The snubber inservice inspection requirements of Paragraphs IWF-5200(a), IWF-5200(b), IWF-5300(a), and IWF-5300(b) are not addressed in this Inservice Inspection Plan. The extent, frequency, and acceptance standards for snubber assembly testmg and inspection will be in accordance with Pilgrim Technical Specification 3.6.I.
1.2.3 Alternative requirements to ASME Section XI,1989 Edition, are set forth in l.
Section 4.0 of the Inservice Inspection Plan. Alternative requirements are in accordance with 10 CFR 50.55a and ASME Section XI.
1.2.4 With the exception of exanunations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, mservice inspections shall be performed in accordance with Inservice Inspection Program B as outlinQ in l
IWA-2412, IWB-2412, IWC-2412, and IWD-2412 of ASME Section XI. The l
inspection schedule for the Third Interval is divided into three periods such that approximately one third of the inspections will be completed every period.
Successive inspections shall be in accordance with IWB-2420, IWC-2420, and Code Case N-491, paragraph -2420. Deviations to inspection schedules may l
occur provided compliance with Code Requirements is maintamed I-1.2.5 ' The commercial operatmg license date for the Pilgrim Nuclear Power Station was June 8,1972. As allowed by ASME Section XI, Paragraph IWA-2430(e), the Second Inspection Interval was =tandad to June 30,1995, 1.3 System Classification
'1.3.1 At the time Pilgrim Station was constructed, the ASME Boiler and Pressure l
Vessel Code only covered nuclear vessels and associated piping up to and including the first isolation or check valve. Therefore, piping, pumps, and valves r
were built primarily to the rules of USAS B31.1.0-1967 Edition. Piping modifications such as the recirculation system pipe replacement were constructed to ASME Section III.
1.3.2 The quality group classification system for water, steam, and radioactive waste f
i.
o drJa= components important to the safety of water-cooled nuclear power l
plants is established by NRC Regulatory Guide 1.26, Revision 3, in conjunction with 10CFR 50.55a. Regulatory Guide 1.26, " Quality Group Classification and Standards", defines the Quality Group Classification System consisting of four Quality Groups, A through D. The definition of Quality Group A (Class 1)is provided by 10 CFR 50.2 under " Reactor Coolant P: essure Boundary". The definitions of Groups B, C, And D (Class 2, Class 3, and ISI non-classed, respectively) are provided by Regulatory Guide 1.26.
I l-2
Pilgrim Station 3rd Interval t
Inservice Inspection Plan j
Program Amendment 98-01
{
t 4
l l
2.2 Piping Isometric Drawbi Table 2.2 provides a listing of the Piping Isometric Drawings for systms subject to inservice inpsection. These drawings identify pipe welds, flange and valve bolted connections, pumps, valves,~ integral attachments, and pipe supports that are within the non-exempt piping boundaries. In addition, system identifications, locations, room names, pipe size, and configuration are identified. Piping and components that 'are exempt from nondestmetive and visual examination in accordance with ASME Section XI, Paragraphs IWB-1220, IWC-1220, and IWD-1220 are not normally depicted on these drawings. If exempt piping or components are shown,.
it is for information only.
TABLE 2.2 PIPING ISOMETRIC DRAWINGS ISI I O ISOMETRIC LEGEND ISI WELD MAP l
ISI-E206A FUEL POOL COOLING HEAT EXCHANGER INTEGRAL ATTACHMENTS ISI-E207A&B RHR HEAT EXCHANGER ISI COMPONENT DRAWING ISI-E209A RBCCW HEAT EXCHANGER INTEGRAL ATTACHMENTS,
ISI-E122A TBCCW HEAT EXCHANGER INTEGRAL ATTACHMENTS
. ISI-P202A RBCCW PUMP SUPPORTS f.
ISI-P203A RHR PUMP INTEGRAL ATTACHMENTS l
ISI-P215A CORE SPRAY PUMP INTEGRAL ATTACHMENTS j
ISI I 1-ISH1 MAIN STEAM SYSTEM MAIN STEAM & DRAIN MANIFOLD I
PIPING ISI WELD MAP ISII l-ISH2 MAIN STEAM SYSTEM MAIN SIhAM & DRAIN MANIFOLD PIPING ISI WELD MAP ISI I 2-0 RECIRCULATION LOOP DETAILS ISI I 2R-A NUCLEAR BOILER SYSTEM REACTOR RECIRCULATION PIPING LOOP A ISI WELD MAP i
2-3
1
/
Pilgrim Station 3rd Interval Inservice Inspecticn Plan Program Amendment 98-01 TABLE 2.2 (con't)
PIPING ISOMETRIC DRAWINGS ISI I 2R-B NUCLEAR BOILER SYSTEM REACTOR RECIRCULATION PIPING LOOP B ISI WELD MAP ISII3-1 CRD 13YDRAULIC SYSTEM REACTOR CRD PIPING ISI WELD MAP ISI I 6-1 CONDENSATE & FEEDWATER SYSTEM FEEDWATER LOOP A & LOOP B ISI WELD MAP ISI I 6-1 A CONDENSATE & FEEDWATER SYSTEM FEEDWATER LOOPS A & B ISI WELD MAP ISI I 10-1 RESIDUAL HEAT REMOVAL SYSTEM, RHR PIPING LOOPS A & B ISI WELD MAP ISI I 10-1 A RESIDUAL HEAT REMOVAL SYSTEM RHR SUPPLY ISI WELD MAP ISI I 10-1B RESIDUAL HEAT REMOVAL SYSTEM RHR PUMP SUCTION CROSS CONNECTION ISI WELD MAP i
l ISI I 10-lC RESIDUAL HEAT REMOVAL SYSTEM, FUEL POOL COOLING TO RHR SUCTION ISI WELD MAP ISI I 10-2A RESIDUAL HEAT REMOVAL SYSTEM RHR PUMPS P-203 A
& P-203C SUCTION ISI WELD MAP ISI I 10-2B RESIDUAL HEAT REMOVAL SYSTEM RHR PUMPS P-203B
& P-203D SUCTION ISI WELD MAP ISI I 10-3A RESIDUAL HEAT REMOVAL SYSTEM PUMPS P-203 A & P-203C DISCHARGE ISI WELD MAP l
ISI I 10-3B RESIDUAL HEAT REMOVAL SYSTEM PUMPS P-203B & P-203D DISCHARGE ISI WELD MAP ISII 10-4ASHI RESIDUAL HEAT REMOVAL SYS'EM, DISCHARGE TO DRYWELL & TORUS ISI WELD MAP ISII 10-4 ASH 2 RESIDUAL HEAT REMOVAL SYSTEM DISCHARGE TO DRYWELL & TORUS ISI WELD MAP 2-4
/
Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 TABLE 2.2 (con'0 PIPING ISOMETRIC DRAWINGS ISII 10-4BSHI RESIDUAL HEAT REMOVAL SYSTEM RHR SYSTEM X-CONNECT DISCHARGE ISI WELD MAP t
ISII 10-4BSH2 RESIDUAL HEAT REMOVAL SYSTEM RHR SYSTEM X-l CONNECT DISCHARGE ISI WELD MAP ISII 10-5BSH1 RHR & CORE SPRAY SYSTEMS RHR & CORE SPRAY j
ISII 10-5BSH2 RHR & CORE SPRAY SYSTEMS RHR & CORE SPRAY L
ISI I 11-1
. STANDBY LIQUID CONTROL SYSTEM REACTOR INJECTIONISI WELD MAP ISII 12-ISH1 REACTOR WATER CLEANUP SYSTEM SUCTION & RPV DRAIN ISI WELD MAP ISII 12-ISH2 REACTOR WATER CLEANUP SYSTEM SUCTION & RPV DRAIN ISI WELD MAP I
ISI I 12-2 REACTOR WATER CLEANUP SYSTEM HEAT EXCHANGER E208 DISCHARGE ISI WELD MAP ISI I 12-3 RWCU SYSTEM HEAT EXCHANGER PIPING ISI WELD l
l MAP j
ISI I 13-1 REACTOR CORE ISOLATION COOLING SYSTEM TURBINE STEAM FLOW MS LINE ISIWELD MAP ISII13-2 REACTOR CORE ISOLATION COOLING SYSTEM RCIC PUMP SUCTION LINE ISI WELD MAP ISI I 13-3 REACTOR CORE ISOLATION COOLING SYSTEM RCIC TURBINE EXHAUST ISI WELD MAP ISI I 13-4 REACTOR COR's ISOLATION COOLING SYSTEM PUMP SUCTION FROM CONDENSATE ISI WELD MAP ISI I 13-5 REACTOR CORE ISOLATION COOLING SYSTEM PUMP SUCTION FROM CONDENSATE ISI WELD MAP 2-5
f Pilgrim Station 3rd Int:rval Inservice Inspection Plan Program Amendnu.t 98-01 TABLE 2.2 (con't)
PIPING ISOMETRIC DRAWINGS ISI I 14-1 CORE SPRAY SYSTEM PUMPS P215A & P215B DISCHARGE ISI WELD MAP ISI I 14-2A CORE SPRAY SYSTEM A TRAIN ISI WELD MAP ISI I 14-2B CORE 5.MY SYSTEM B TRAIN ISI WELD MAP ISII 23-1 HIGH PRESSURE COOLANT INJECTION SYSTEM, TURBINE STEAM SUPPLY & DISCHARGE ISI WELD MAP l
ISI I 23-2 HIGH PRESSURE COOLANT INJECTION SYSTEM TURBINE l
STEAM SUPPLY ISI WELD MAP ISI I 23-3 HIGH PRESSURE COOLANT INJECTION SYSTEM TURBINE EXHAUST SYSTEM ISI WELD MAP ISI I 23-4 HIGH PRESSURE COOLANT INJECTION SYSTEM, HIGH PRESSURE COOLANT ISI WELD MAP l
ISI I 23-5 HIGH PRESSURE COOLANT INJECTION SYSTEM, HIGH PRESSURE COOLANT ISI WELD MAP l
i ISII 29-ISHI SERVICE WATER SYSTEM SUPPLY & RETURN E209A &
i E209B & E122A & E122B 1
ISII 29-ISH2 SERVICE WATER SYSTEM SERVICE WATER PUMPS DISCHARGE ISI WELD MAP i
ISII 30-ISHI REACTOR BUILDING CLOSED COOLING WATER SYSTEM i
PUMPS DISCHARGE ISI WELD MAP ISII 30-ISH2 REACTOR BUILDING CLOSED COOLING WATER SYSTEM, i
REACTOR BUILDING l
_ ISI I 30-2SH1 REACTOR BUILDING CLOSED COOLING WATER SYSTEM, l
REACTOR BUILDING i
l l
ISI I 30-2SH2 REACTOR BUILDING CLOSED COOLING WATER SYSTEM REACTOR BUILDING l
l 2-6
J Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 TABLE 2.2 (con't)
PIPING ISOMETRIC DRAWINGS ISI I 30-3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM INTEGRAL ATTACInfENTS ISI I 50-1 CONTAINMENT ATMOSPHERIC CONTROL SYSTEM DRYWELL & TORUS PURGE & VENT PIPING ISI WELD MAP ISI I 54-1 NUCLEAR BOILER SYSTEM REACTOR VESSEL WELDS &
NOZZLES ISI WELD MAP ISI I 54-2 NUCLEAR BOILER SYSTEM REACTOR VESSEL CLOSURE HEAD WELDS & NOZZLES ISI I 54-3 NUCLEAR BOILER SYSTEM REACTOR VESSEL BOTTOM HEAD WELDS & NOZZLES ISII54-4 NUCLEAR BOILER SYSTEM REACTOR VESSEL NOZZLES ISI WELD MAP 2-7
1
.J' Pilgrim Station 3rd Interval Inservice Inspection Plan i
Program Amendment 98-01 1
SECTION 3.0 INSERVICE INSPECTION TABLES This section provides a summary listing of all items subject to inservice inspections during the Third Inservice Inspection Interval at Pilgrim Nuclear Power Station.
. 3.1 ASME Section XI Inservice Inspections The ASME Section XI Inservice Inspection Smamary Table 3.1 provides the following information:
i 3.1.1 Exammation Category This column lists the exammation category as identified in ASME Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and Code Case N-491, paragraph -2500-1. Only those exammation categories applicable to Pilgrim Station are identified.
l 3.1.2 Item Number and Description of Components Exammed l
These columns list the item number and description as defmed in ASME Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and Code Case N-491, paragraph -2500-1. Only those item numbers applicable to Pilgrim Station are identified.
l 3.1.3 Number of Components This column lists the total population of components potentially subject to exammation. The number of components actually examined during the inspection interval will be based upon the Code requirements for the subject item number (e.g., 25% of Exammation Category B-J, item Number B9,11 components will be av= mined during the inspection interval).
3.1.4 Evamincion Method l
The column lists the exammation method (s) required by ASME Section XI, Tables IWB-2500-1, IWC-2500-1, IWD 2500-1, and Code Case N-491, paragraph -
2500-1.
3.1.5 Relief Request Number i
This column provides a listing of applicable relief requests. If a relief request number is identified, see the corresponding relief request in Section 4.4.
3.2 COMPONENTS SCHEDULED FOR EXAMINATION IN THE THIRD TEN YEAR INTERVAL Table 3.2 details components selected for exammation.
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)
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G G G G G G G G G G G G G G G G G l
H H l
Reference:
IWD-2500, Table IWD-2500-1 Examination Category:
D-B ltem Number:
D2.10 -
==
Description:==
Alternate Provisions for the Pressure Testing of Salt Service Water Pumps Component Numbers:
P 208A P-208B P-208C P-208D P-208E CODE REQUIREMENT Table IWD-2500-1, Examination Category D-B, Item Number D2,10 requires that system functional (pressure) test and system hydrostatic test be performed on all pressure retaining components.
As addassed m Section 4.1 of this Third Interval ISI Plan, Code Case N-498-1 has been approved for use at the Pilgrim Station by the NRC. In accordance with Code Case N-498-1, a system pressure test would be performed each interval in lieu of the system hydrostatic test.
BASIS FOR RELIEF The Salt Service Water System has been designated Class 3 and provides cooling to the Reactor Building and Turbine Building Closed Cooling Water Systems. The system includes 5 wet-pit type centrifugal pumps which are largely submerged under water.
System pressure testing of the Salt Service Water System pumps and associated discharge lines would require disassembly and removal, special testing, and reassembly of the pumps. The requirements to remove the pumps for the sole purpose of performing a test of the pressure boundary has a negligible impact on plant safety and a disproportionate impact on expenditures of plant manpower. The integrity and function of the pumps is already verified by the performance of periodic full flow tests. In addition, in the unlikely event of a pump failure, the installed spare pump l
could provide the required function.
l l
4-23 l
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Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-11 REVISION 2 (Page 2 of 2)
BASIS FOR RELIEF (Cont.)
i Reliefis requested from the requirements to perform a system pressure test on the Salt Service Water pumps up to the expansion joints in the pump discharge lines on the basis ofimpracticality and a negligible effect on plant safety.
PROPOSED ALTERNATE PROVISIONS VT-2 examination of the pump discharge piping up to the expansion joints will be conducted during system functional pressure tests performed on the remainder of the system once each period as required by ASME Section XI.
i APPLICABLE TIME PERIOD Reliefis requested for the third ten-year interval of the Pilgrim Station Inservice Inspection Program, beginning July 1,1995.
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4-24 l
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=
Pilgrim Station 3rd Interval i
Inservice Inspection Plan Program Amendment 98-01 I
RELIEF REOUEST NUMBER: PRR-13 REVISION 2 Page1 of5 COMPONENT IDENTIFICATION Code Class:
2
Reference:
IWC-2500, Table IWC-2500-1 Exammation Category:
C7.30, C7.40, C7.70 and C7.80 l
i
==
Description:==
Alternate Provisions for Pressure Testing of Code Class 2 Piping and Valves Penetrating Containment l
Where the Balance of Piping is Outside the Scope of Section XI X-46D M227 Sh.1 1"-HCB-45 Drywell Level Line CC N-522 - no VT-2 CC N-522 - Bubble test or l
exam equivalent VT-2 during i
T3ve A test
)
l X-219 M227 Sh.1 4"-HCB-45 HPCI Turbine Exhaust CC N-522 - no VT-2 CC N-522 - Bubble test or l
Vacuum and Hydrogen exam equivalent VT-2 during l
Recombiner Vent Type A and/or C tests.
l X-228B M227 Sh.1 1"-DC-45 Torus Pressure CC N-522 - no VT-2 CC N-522 - Bubble test or l
l exam equivalent VT-2 during 1
l Type A test.
I X-25 M227 Sh.1 18"-HM-45 Vent from Drywell CC N-522 - no VT-2 CC N-522 - Bubble test or l
exam equivalent VT-2 during i
Type C test.
X-26 M227 Sh.1 18"-HM-9 Vent to Drywell CC N-522 - no VT-2 CC N-522 - Bubble test or exam ex[mvalent VT-2 during Type A test.
X-205 M227 Sh.1 20"-HM-45 Torus Purge Inlet CC N-522 - no VT-2 CC N-522 - Bubble test or exam equivalent VT-2 during T>pe A test.
I l
i 4-26 L
Pilgrim Station 3rd Intcrval Inscrvice Inspection Plan Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-13 REVISION 2 Page 2 of 5 Gd$M$3# !
$2 f0!$!$i31i l
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X-227 M227 Sh.1 20"-HM-45 Torus Purge Exhaust CC N-522 - no VT-2 CC N-522 - Bubble test or i
Vacuum Relief and exam equivalent VT-2 during Direct Torus Vent Type C test.
X-29E M239 Sh.1 1"-DC-45 PASS Train 'A' CC N-522 - no VT-2 CC N-522 - Bubble test or Drywell Gas Sample exam equivalent VT-2 during Line (45-HO-350A to Type C test.
SV5065-33A)
X-15E M239 Sh.1 1"-DC-45 PASS Train 'B' CC N-522 - no VT-2 CC N-522 - Bubble test or Drywell Gas Sample exam equivalent VT-2 during Line (45-HO-350B to Type C test.
SV5065-31B)
X-106A-b M239 Sh.1 1"-DC-45 PASS Train 'A' CC N-522 - no VT-2 CC N-522 - Bubble test or i
Drywell Gas Sample exe.m equivalent VT-2 during l
Line (45-HO-352A to Type C test.
SV5065-14A)
X-50A-d M239 Sh.1 1"-DC-45 PASS Train 'B' CC N 522 - no VT-2 CC N-522 - Bubble test or Drywell Gas Sample exam equivalent VT-2 during Line (45-HO-352B to Type C test.
SV5065-13B)
X-46F M239 Sh.1 1"-DC-45 PASS Train 'A' CC N-522 -- no VT-2 CC N-522 - Bubble test or Drywell Return Line exam equivalent VT-2 during (45-HO-354A to Type C test.
SV5065-26A)
X-22 M220 Sh.2 3"-HCB-31 Instrument Air CC N-522 to allow use Bubble test or equivalent oflower test pressure VT-2 at Instrument Air (45 psig) than N.O.P. (code pneumatie N.O.P.(99 psig) and no test)
VT-2 during App. J No relief required for Type C test.
hydro requirement (CC N-522 not needed)
X-228J M239 Sh.1 1"-DC-45 PASS Train 'A' Torus CC N-522 - no VT-2 CC N-522 - Bubble test or Gas Sample Line (45-exam equivalent VT-2 during HO-357A to SV5065-Type C test.
l 11A) l X-228C M239 Sh.1 1"-DC-45 PASS Train 'B' Torus CC N-522 -- no VT-2 CC N-522 - Bubble test or Gas Sample Line (45-exam equivalent VT-2 during HO-357B to SV5065-Type C test.
ISB)
X-228K M239 Sh.1 1"-DC-45 PASS Train 'B' Torus CC N-522 -- no VT-2 CC N-522 - Bubble test or Return Line (45-HO-exam equivalent VT-2 during 354B to SV5065-278)
Type C test.
4-27 l
l_
o Pilgrim Station 3rd Int:rval Inservice Inspection Plan Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-13 REVISION 2 Page 3 of 5 CODE REQUIREMENT ASME Section XI, Table IWC-2500-1, Examination Category C-H, requires the performance of visual VT-2 examination on accessible piping during system pressure tests on Code Class 2 pressure retaining components.
BASIS FOR RELIEF This request for reliefis based on two issues: 1) Use of Code Case N-522 (with alternate provisions l
from Draft Regulatory Guide DG-1050) and 2) Inspection limitations based on impracticality or ALARA
- 1) Use of Code Case N-522 (with alternate orovisions)
Code Case N-522 (with alternate provisions from Draft Regulatory Guide DG-1050) allows the use of air instead of water as the test medium and use of the Appendix J peak calculated contamment pressure (45 psig at Pilgrim NPS) in lieu of the test pressure l
required for the 10 year code hydrostatic test. The VT-2 exammation requirement for the
[
code 40 month system pressure test is also climinated.
Boston Edison believes that the use of Appendix J test methods in accordance with Code i
Case N-522 for Class 2 piping and valves at containment penetrations is an acceptable I
alternative to Section XI pressure testing since the piping and valves listed in Table I are
]
categorized as Class 2 due to their containment pressure boundary function. The balance of the systems are outside the scope of Section XI. Appendix J test methods and criteria are the accepted means for the verification ofleak-tight integrity of containment pressure-l l
boundary components and therefore provide an acceptable level of quality and safety. Use of code hydrostatic test methods with VT-2 examination is not a practical option for the subject piping and valves since the containment isolation valves (CIV) are designed for use in air systems. Pressure testing with water could adversely impact the senice life of the CIVs.
- 2) Inspection limitations based on impracticality or ALARA Certain piping segments (Table 2) are located in areas where access is difficult causing l
direct VT-2 examination to be impractical. Boston Edison believes this constitutes a hardship with no compensating increase in the level of quality and safety. A significant staging and, in some cases, insulation removal effort would be required for the piping segments listed in Table 2 below to be bubble tested (or tested using equivalent methods) with VT-2 examiners (using Code Case N-522 during Appendix J testing) to detect the source of through-wall leakages. The original design did not anticipate direct visual examination. System pressures and temperatures for these piping segments and valves during normal plant operations are typically low (1.5 psig & 100 degrees F) with the most severe senice conditions imposed by periodic Appendix J testing at the peak accident test l
pressure of 45 psig. There is no known degradation mechanism or normal operating j
4-28 t
o-Pilgrim Station 3rd Interval Inservice Inspection Plan i
Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-13 REVISION 2 Page 4 of 5 condition that would adversely impact the structural integrity of this piping. Direct VT-2 exammation would not significantly increase the level of quality and safety since the method can only detect through-wall dcf-cts. A flaw that has not propagated entirely through-wall could conceivably have a negativa, impact on piping structural integrity and
(
still not be detected by a VT-2 exam. Therefoie, a direct VT-2 examination at nommal operating pressures does not constitute a verification of piping structural integrity, but only ofleak-tightness. Appendix J testmg of this piping provides an adequate level of quality :
and safety since it is the accepted means to verify the leak-tight integrity of the pnmary l
contamment system.
l PROPOSED ALTERNATE PROVISIONS I
Boston Edison proposes the use of Code Case N-522 at Pilgrim Nuclear Power Station with the l.
following modifications as an alternative to the Section XI Category C-H pressure test n;quirements a
for piping and valves at containment penetrations where the balance of piping is outside the scope of Section XI:
Boston. Edison shall perform 10 CFR 50 Appendix J leakage tests on the contamment per.h tion piping and valves listed in Table I at the peak calculated contamment pressure (45 j-psig) in accordance with Pilgrim Station procedures as an alternative to the Section XI 40 month system pressure test Code Items C7.30 and C7.70 and VT-2 requirement.
Boston Edison shall also perform 10 CFR 50 Appendix J leakage tests on the contamment
[
e penetration piping and valves listed in Table I at the peak calculated containment pressure (45 l
psig) in accordance with Pilgrim Station procedures. Test procedures will permit the detection and location of through-wall leakage by VT-2 certified examiners on accessible piping as an l
alternative to the Section XI ten year hydrostatic test, Code Items C7.40 and C7.80 requirement.
Piping segments located in areas where direct VT-2 exammation is considered impractical are listed in Table 2. These segments shall be tested using Appendix J test procedures but will not l
be VT-2 visually examined.
L l
I I
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4-28a l
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r l
Pilgrim Station 3rd Interval i
Inservice Inspection Plan Program Amendment 98-01 l
f RELIEF REOUEST NUMBER: PRR-13 l
REVISION 2 Page 5 of 5 l
WENER'M M:
l i
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m X-29E PASS Train 'A' Drywell approx. 39 feet of 1" pipe Impractical due to extensive staging Gas Sample Line from valve 45-HO-350A (piping is 20 feet above floor) and up to the elevation 74*
insulation removal on the 5l' floor penetration.
elevation of the Reactor Building X-29E PASS Train 'A' Drywell Approximately 28 feet of ALARA -adverse radiological Gas Sample Line 1" pipe from the elevation conditions in the Fuel Pool Heat i
74' floor penetration to Exchanger Room due to the pipe's valve SV5065-33A proximity to the FPC pumps and piping X-15E PASS Train 'B' Drywell Approximately 17 feet of ALARA - adverse radiological l
Gas Sample Line 1" pipe from valve 45-HO-conditions in the RWCU Heat 350B to the north wall Exchanger Room where extensive penetration in the RWCU staging and insulation removal i
Heat Exchanger Room above the RWCU heat exchanger would be required X-15E PASS Train 'B' Drywell Approximately 32 feet of Impractical due to extensive staging l
Gas Sample Line 1" pipe from the north wall (piping is 18-23 feet above floor) i penetration of the RWCU and insulation removal above the Room up to the elevation 5l' elevation of the Reactor 74' floor penetration Building X-50A-d PASS Train 'B' Drywell approximately 6 feet of 1" ALARA - extensive staging and Gas Sample Line pipe from valve 45-HO-insulation removal adjacent to the 352B to valve SV5065-reactor building pedestal inboard of 13B the torus in a high radiation area.
l X-32A Rx. Pressure Boundary approximately 3 feet of I" ALARA - extensive staging adjacent Leak Detection System pipe from valve 45-HO-to the reactor building pedestal l
Return Line to Drywell 360 to valve SV5065-92 inboard of the torus in a high radiation area.
APPLICABLE TIME PERIOD Reliefis requested for the third ten-year interval of the Pilgrim Station Inservice Inspection Program, beginning July 1,1995.
i 4-28b I
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'4 Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01
'l RELIEF REQUEST NIIMBER: PRR-18 l
(Page 1 of 3)
WITHDRAWN l
4
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__7 Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 1
RELIEF REQUEST NUMBER: PRR.18
' (Page 2 of 3) l WITHDRAWN l
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l 1
4-36
Pilgrim Station 3rd Interval Inservice Inspection Plan l.
Program Amendment 98-01 RELIEF REQUEST NUMBER: PRR-18 (Page 3 of 3) l l
4-37
Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 RELIEF REQUEST NUMBER: PRR-22 (Page 1 of 2)
WITHDRAWN 4-42
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Pilgrim Station 3rd Intr,rval Inservice Inspection Plan Program Amendment 98-01 RELIEF REQUEST NUMBER: PRR-22 (Page 2 0f 2)
WITHDRAWN f
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4-43
,___Lu_L-__--___------_-:___--_--_-----___---------_----------------------------------------------------------
Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-24 REVISION 1 (Page1of2)
COMPONENT IDENTIFICATION Code Classes:
I and 2
References:
IWA-2311 (b) and Appendix VII Examination Categories:
B-A, B-D, B-F, B-G-1, B-J, B-M-1, B-O t
C-A, C-B, C-F-1, C-F-2 Item Numbers:
Bl.11, Bl.12, Bl.21, Bl.22. Bl.30, Bl.40, B2.90, B3.100, B5.10, B5.130, B6.20, B6.30, B6.40, B6.180, B9.11, B9.12, B9.31, B12.40, B14.10 Cl.10, Cl.20, C5.11, C5.51
==
Description:==
Exemption from the schedule requirement of Appendix Vil, Paragraph Vll-4240, Annual Training Component Numbers:
All Class 1 and 2 components requiring ultrasonic examination CODE REQUIREMENT Sub-paragraph IWA-2311(b) specifies that the training, qualification, and certification of ultrasonic examination personnel shall also comply with the requirements of Appendix VII.
Appendix VII provides requirements for the employer's written practice, qualification of ultrasonic examiners, qualification records, and the minimum content ofinitial training courses for the ultrasonic examination method in addition to those required in SNT-TC-1 A.
BASIS FOR RELIEF Our Third Ten-Year Insenice Inspection interval began on July 1,1995, and the annual training for our NDE personnel should be complete by June 30,1996, to comn'y with Paragraph VII-4250.
Since we do not have an instructor qualified to Paragraph VII-414J and the next readily available course is in November 1996, it was not practical to meet the annual training requirements by June 30,1996. Thus, Boston Edison requests relief from the schedule from July 1995 to December 1996, to comply with the annual training requirement of Appendix VII, Paragraph VII-4240.
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Pilgrim Station 3rd Interval Inser5 ice Inspection Plan Program Amendment 98-01 RELIEF REOUEST NUMBER: PRR-24 REVISION 1 (Page 2 of 2)
The training and certification program to comply with Appendix VII will be fully implemented by June 1997. The program includes course material, procedures, and test specimens. We are revising our training and certification procedure (Quality Assurance Group Procedure No.10.09) to meet the requirements of Appendix Vll. An individual will complete NDE instructor training in November l
1996, and we will be in compliance with the subsequent annual training requirements beginning l
June 1997.
PROPOSED ALTERNATE PROVISIONS The Enclosure provides a summary of BECo qualified ultrasonic examination personnel. These personnel currently comply with ASME Section XI requirements for ultrasonic qualifications in accordance with Sub-Article IWA-2310 and code interpretation Xl-1-92-42 which recognize the continuity of existing certifications. Thus, BECo fully complies with ASME Section XI by using the provisions of Sub-Article IWA-2310.
As an alternative to meeting the annual training requirement of Paragraph VII-4240, BECo NDE personnel are scheduled in 1996 for a 40-hour ultrasonic course in ASME XI examination methods.
The course does not qualify to Appendix VII provisions since the instructors are not code defined NDE instructors pursuant to Paragraph VII-4140. This 40-hour specialized course is considered to be an equal substitute for the 10-hour annual training by a qualified NDE instructor because the course duration, materials, and instructor's credentials are at least equivalent to code requirements, resulting in a equal level of quality and safety in the ISI examinations.
The 40-hour ultrasonic course and the existing certification of BECo NDE personnel provide adequate, basis for conducting the on-line ISI examinations beginning October 1996. Further, the Appendix VII requirements for Refueling Outage (RFO) #11 examinations, currently planned for February 1997, will be met through the use of qualified BECo contractor personnel. The alternate provision does not impact quality of safety, since ASME Section XI requirements will be met by complying with Paragraphs IWA-2310 and VII-4240 for ISI examinations. Thus, the relief request meets the requiremems of 10 CFR 50.55a(a)(3)(i) in that an acceptable level of quality and safety is maintained.
APPLICABLE TIME PERIOD Reliefis requested for the Third Ten-Year interval of the Pilgrim Station Inservice Inspection Program beginning July 1,1995 until December 1996 for implementing annual training requirements.
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Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 ENCLOSURE TO PRR-24 Summary of Boston Edison Company NDE Oualified Personnel Three individuals are certified in ASME Section XI ultrasonic exammation methods at Boston Edison Company.
Below is a summary of their qualifications.
Individual A Certified from 1972 to 1982 as UT Level II while in the U.S. Navy and Stone &
Webster Engineering Corporation.
Certified as an ASNT Level III from 1982 to present (by exammation).
Certified as a BECo NDE Level III from 1983 to present (by exammation).
Documented classroom training in ultrasonic examination is 209 hours0.00242 days <br />0.0581 hours <br />3.455688e-4 weeks <br />7.95245e-5 months <br />.
Individual B Certified as a NDE Level III from 1980 to present while employed at Stone & Webster
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Engmeering Corporation, Yankee Atomic Electric Company, and Boston Edison Company (by examination).
Certified as ASNT Level III from 1984 to present (by examination).
Documented classroom training in ultrasonic exammation is 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />.
Individual C Certified as a Level I in 1992 at Boston Edison Company.
Certified as Level II in 1995 at Boston Edison Company.
Documented classroom training in ultrasonic examination is 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br />.
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Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 1
NRC CORRESPONDENCE i
- a. BECo Letter 95-091, dated 9/1/95. E.T. Boulette to NRC, " Third Ten-Year Inservice Inspection Plan PNPS (ISI)".
- b. NRC Letter 95-189, dated 12/6/95. R.B. Eaton to E.T. Boulette, " Request for Additional Information on the Pilgrim Nuclear Power Station Third Ten-Year Interval Inservice Inspection Program Plan and Associated Requests for Relief".
BECo Letter 96-009, dated 2/15/96. " Boston Edison Company Response to NRC Request for c.
l Additional Information on Pilgrim Third Ten-Year ISI Program (TAC No. M93398)"
- d. BECo Letter 96-035, dated 4/16/96.-- E.T. Boulette to NRC, " Revised Table Related to RPV Nozzle Exanunation, Pilgrim Plant Relief Request -9, 'Ihird Ten-Year ISI Program (TAC No. M93398)"
BECo Letter 96-067, dated 7/12/96. E.T. Boulette to NRC, " Revised Pilgrim Relief Request (PRR)-24, l
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Pilgrim Third Ten-Year Inservice Inspection Program".
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NRC Letter 96,141, dated 9/27/96, Gary S. Vissing to E.T. Boulette, "NRC SER on RHR/FPC Intertie ReliefRequest" i
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BECo letter 96-091, dated 10/30/96, E.T. Boulette to NRC, " Pilgrim Station 1996 On-Line and 1997 Refueling Outage !I Inservice Inspection (ISI) Plan.
- h. BECo Letter 96-105, dated 11/20/96. E.T. Boulette to NRC, " Pilgrim Refueling Outage #11, ISI Relief From, (a) ASME,Section XI Inspections, and (b) Generic Letter 88-01, IGSCC Inspections".
- i. NRC Letter 97-007, dated 2/18/97. P.D. Milano to E.T. Boulette, " Pilgrim Nuclear Power Station -
Request Pertaining to Relief from ASME XI Inspections and Generic letter (GL) 88-01, Intergranular Stress Corrosion Cracking (IGSCC) Inspections".
- j. BECo Letter 97-010, dated 2/5/97. E.T. Boulette to NRC, " Withdrawal of Pilgrim Refueling Outage (RFO) #11 ISI Relief Request #1 and #2 (ASME Section XI Inspections) and Revision to RFO #11 ISI Plan Scope".
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- k. - BECo Letter 97-015, dated 2/10/97. E.T. Boulette to NRC, " Withdrawal of Pilgrim Relief Request (PRR)-7, Pilgrim Third Ten-Year Inservice Inspection (ISI) Program" 5-2 I-
Pilgrim Station 3rd Interval Inservice Inspection Plan Program Amendment 98-01 1.
NRC Letter 97-026, dated 3/20/97. P.D. Milano to E.T. Boulette, " Evaluation of the Third Ten-Year Interval Inspection Program Pian, and Associated Requests for Relief for Pilgrim Nuclear Power Station".
- m. BECo Letter 97-033, dated 3/18/97. E.T. Boulette to NRC, " Inspection of Core Spray Piping Internals at Pilgrim" BECo Letter 97-038, dated 4/2/97. E.T. Boulette to NRC, " Supplementary Information on Inspection of n.
Core Spray Piping Internals at Pilgrim".
NRC Letter 97-041, dated 4/18/97. P.D. Milano to E.T. Boulette, " Assessment of Core Spray System o.
Piping Inspections and Flaw Evaluations at Pilgrim Nuclear Power Station."
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BECo Letter 97-068, dated 6/25/97. N.L. Dermond to NRC, " Pilgrim Station 1996 On-Line and Refueling Outage 1 I Inservice Inspection Report"
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BECo Letter 97-081, dated 8/8/97. N.L. Desmond to NRC, " Response to Request for Additional Information on Cracking of Core Spray Internal Piping" i
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