ML16341F384
| ML16341F384 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/25/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16341F383 | List: |
| References | |
| NUDOCS 8911030104 | |
| Download: ML16341F384 (68) | |
Text
ENCLOSURE gP,R RED L
p.
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLANS AND RELIEF REQUESTS PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1
AND 2 DOCKET NUMBERS:
50-275 AND 50-323 I.
INTRODUCTION Technical Specification 4.0.5 for the Diablo Canyon Nuclear Power Plant, Units 1
and 2, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASHE) Boiler and Pressure Vessel Code Class 1,
2, and 3 components shall be applicable as follows:
Inservice Inspection of ASME Code Class 1, 2, and 3
components shall be performed in accordance with Section XI of the ASHE Code and applicable Addenda as required by 10 CFR 50.55a(g),
except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i).
Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for his facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASHE Code requirement.
After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i),
the Commission may grant relief and may imoose alternative requirements that are determined to be authorized by law, will not endanger life or property or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
By letter dated June 23, 1989, the Pacific Gas and Electric Company (the Licensee) submitted Revisions 7 and 4 of the First Ten-Year Interval Inservice Inspection (ISI) Program Plans for the Diablo Canyon Power Plant, Units 1 and 2, respectively.
The ISI Program Plans were written to meet the requirements of the 1977 Edition, Summer 1978 Addenda of Section XI of the BVl >0S0>O4 89lOZ5 PDR ADDCK 05000275 8
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%SHE Boiler and Pressure Vessel
- Code, except that the extent of examination of Class 1 and 2 piping welds was determined by the 1974 Edition, Summer 1975 Addenda as permitted by 10 CFR 50.55a(b)(2)(ii) and as required by 10 CFR 50.55a(b)(2)(iv).
Additional information was submitted by the Licensee in letters dated September 7 and 19, 1989 with regard to Requests for Relief 8 and 9.
The staff, with technical assistance from its Contractor, the Idaho National Engineering Laboratory '(INEL), has evaluated these revisions to the program plans and the requests for relief from certain ASME Code requirements determined to'e impractical for the Diablo Canyon Power Plant, Units 1
and 2, during the first inspection interval.
II.
EVALUATION Revisions 7 and 4 of the ISI Program Plans for Units 1 and 2, respectively, have been evaluated for (a) application of the correct Section XI Code edition and
- addenda, (b) compliance with examination and test requirements of Section XI, (c) acceptability of the examination
- sample, (d) compliance with commitments made by the Licensee prior to plant operation, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from impractical Section XI Code requirements.
The staff has determined that the Licensee's ISI Program Plans, Revisions 7 and 4 for Units 1 and 2, respectively, with the exception of Relief Request 8 (in part), reflect compliance with the requirements listed above.
The revised ISI Program Plans incorporate changes in response to the NRC staff's Safety Evaluation Reports (SER) dated December 14, 1988.
These revisions contain a number of relief requests that have been revised,
- added, or deleted.
The information provided by the Licensee in support of the revised and added requests for relief from impractical requirements has been evaluated and the bases for granting relief from those requirements are documented below.
Unless otherwise stated, reference to the Code refers to the ASNE Code,Section XI, 1977 Edition, Summer 1978 Addenda.
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~ 4 A.
Re uests for Relief NDE-006 Unit I and NDE-007 Unit 2 Shell and Head Circumferential Welds Tubesheet-to-Shell Welds and Nozzle Welds in Class 2 Pressure Vessels Relief Requests NDE-006 (Unit I) and NDE-007 (Unit 2) were previously evaluated in the NRC SERs dated December 14, 1988 and granted provided that volumetric or visual examinations of the subject welds be performed to the extent practical.
The Licensee has revised these relief requests to include the SER condition that volumetric examination be performed to the extent practical for the Excess Letdown Heat Exchanger girth welds, the RHR Heat Exchanger girth welds, and the RHR Heat Exchanger nozzle-to-shell welds.
The SER condition that visual examination of the Seal Injection Filter girth welds be performed to the extent practical
'I has been determined to be not practical based on the design of the Seal Injection Filters and the high radiation levels in those areas
- and, thus, was not incorporated into the revised relief requests.
It is concluded that the incorporation of the condition to perform volumetric examination of the subject welds into Relief Requests NDE-006 (Unit I) and NDE-007 (Unit 2) renders these relief requests acceptable.
Therefore, relief is granted for Relief Requests NDE-006 (Unit I) and NDE-007 (Unit 2).
A summary of these relief requests can be found in Table I under numbers NDE-006A and B and in Table 2 under numbers NDE-007A and B.
B.
Re uests for Relief NDE-008 Unit I Class I and 2 Circumferential Pi in Welds Relief Request NDE-008 was previously evaluated and granted in the NRC SER dated December 14, 1988.
The Licensee has revised this relief request to include the following additional Class I and 2 piping welds that were determined to be partially inaccessible during the Unit I second refueling outage:
J S
Code Exam.
Cet.
B-J B-J Code Item Number Mel d Number B9. 11 WIB-171 B9. 11 MI8-276 B-J B9.21 WIB-124 C-F C5.21 WIC-9-1 B-J B9. 11 MIB-313SE B-J B9. 11 MIB-415B B-J B9.11 WIB-416A 8-J B9. 11 MI8-432B B-J B9.11 WIB-433A Code Required Exam.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Surface Vol. and Surf.
Estimated Percent Accessible 75/ vol.,
100% surf.
75% vol.,
100% surf.
60% vol.,
100% surf.
75% vol.,
100/. surf.
75% vol.,
100% surf.
75'%ol.,
100% surf.
75% vol.,
100% surf.
95% surf.
75% vol 100/ surf.
Limitation Valve Valve Limited to 1 inch from Safe End Valve Val ve Valve Valve Surface condition (base metal)
Elbow Based on the limitations encountered during examination of these
- welds, it is concluded that the subject volumetric or surface examinations are impractical to perform to the extent required by the Code.
Therefore, the disposition that relief is granted as requested remains unchanged for Relief Request NDE-008 (Unit 1).
A summary of this relief request can be found in Table 1 under numbers NDE-008A through D.
C.
Re uest for Relief NDE-009 Unit 2 Reactor Pressure Vessel and Pressurizer Nozzle-to-Safe nd Welds Class Circumferential Pi in Welds Branch Pi e Connection Welds and Pi in Inte rail Welded Attachments Class 2 Pi in Inte rail Welded Su ort Attachments and Circumferential Pi in Weld Relief Request NDE-009 was previously evaluated and granted in the NRC SER dated December 14, 1988.
The Licensee has revised this relief request to include the following additional Class 1 and 2 piping welds that were determined to be partially inaccessible during the Unit 2 first and second refueling outages:
j 1
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Code Exam.
Cat.'-F 8-F 8-F Code Item Number 85.10/
85.50
- 85. 10/
85.50 85.20/
85.50 Meld Number WI8-RC-1-1SE MI8-RC-2-1SE WIB-423SE Code Required Exam.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Estimated Percent Accessible 25% vol.,
100% surf.
25%%uo vol.,
100% surf.
90% vol.,
100% surf.
Limitation No scan upstream side:
RPV No scan upstream side:
RPV Nozzle boss 8-J
- 89. 11 MIB-6 8-J 89.11 WIB-39 8-J 89.11 WIB-88 8-J 8-J 8-J 8-J
- 89. 11 MI8-197 89.11 WIB-246 89.11 MIB-291 89.11 WIB-322 8-J
- 89. 11 WI8-RC-2-2 8-J 89.11 MI8-RC-1-2 Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
75% vol.,
100/. surf.
75% vol.,
100% surf.
90% vol.,
100% surf.
90/ vol.,
100%%u surf.
90% vol.,
100% surf.
95% vol.,
100/o surf.
90% vol.,
100% surf.
50% vol.,
100% surf.
50% vol.,
100%%u. surf.
Valve Rupture restraint Elbow intrados Fittings Rupture restraint Support Elbow intrados Limited scan upstream side:
RPV Limited scan upstream side:
RPV 8-J 8-J 8-J 8-J 8-J 8-J 8-K-1 8-K-1 8-K-1
- 89. 21 89.21 89.21 89.21 89.31 89.31 810.10 810.10 810.10 WIB-408 WI8-410A WIB-514 WIB-856 WIB-37 MIB-55 409-3A 898-2 989-29R Surface Surface Surface Surface Vol. and Surf.
Vol. and Surf.
Surface Surface Surface 90/. surf.
90/. surf.
90% surf.
99% surf.
25/o vol 100% surf.
65% vol.,
100% surf.
99% surf.
99% surf.
95% surf.
Code ID band Hanger Hanger Support Branch connection geometry Branch connection Next to wall Clamp Support C-C C3.40 23-36R C-F C5. 21 MIC-1357A C-F C5. 21 WIG-13578 C-F C5. 21 WIC-1357C C-F C5. 21 WIC-1357E Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
Vol. and Surf.
75% vol.,
100% surf.
75/. vol.,
100% surf.
80% vol.,
100% surf.
90%%u. vol.,
100%%u. surf.
Valve Ventilation duct Ventilation duct Penetration Surface 90% surf.
Support
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Based on the limitations encountered during examination of these
- welds, it is concluded that the subject volumetric or surface examinations are impractical to perform to the extent required by the Code.
Therefore, the disposition that relief is granted as requested remains unchanged for Relief Request NDE-009 (Unit 2).
A summary of this relief request can be found in Table 2 under numbers NDE-009A through F.
D.
Re uests for Relief NDE-012 Unit 1
and NDE-015 Unit 2 Steam Generator Nozzle Inside Radius Sections Relief Requests NDE-012 (Unit 1) and NDE-015 (Unit 2) were previously evaluated in the NRC SERs dated December 14, 1988.
Relief from performing the volumetric examination of the nozzle inside radius sections of the steam generator primary inlet and outlet nozzles was granted provided that visual examination of the areas is performed during tube examinations.
After verbal discussions with the Licensee, it was concluded that performing a visual examination is impractical.
Therefore, relief is granted as requested for Relief Requests NDE-012 (Unit 1) and NDE-015 (Unit 2).
A summary of these relief requests can be found in Table 1 under numbers NDE-012A and B and in Table 2 under number NOE-015.
E.
Re vest for Relief 2 Units 1 and 2
H drostatic Test of Class 2 and 3
Com onent Coolin Water S stems and Re uest for RelieF 3
Units 1 and 2
H drostatic Test of Class 2
Com onent Coolin Water Pi in Associated with Containment Penetrations Relief Requests 2 and 3 (Units 1 and 2) were previously evaluated in the December 14, 1988 SERs and denied due to insufficient justification; as a result, the Licensee has deleted these relief requests from the revised ISI Program Plans.
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F.
Re uest for Relief 8'nits 1 and 2
S stem Pressure Test of Class 2
Non-Safet Related S stem Containment Penetrations Code Re uirement:
Section XI, Table IMC-2500-1, Examination Category C-H, Item C7.20 requires a 10Ã visual (VT-2) examination and a
system pressure test during system functional test (IMC-5221) of Class 2
pressure retaining piping each inspection period.
Paragraph IWC-5221(a) states that the nominal operating pressure of the system functional test shall be acceptable as the system test pressure.
Item C7.21 requires a
100% visual (VT-2) examination during a system hydrostatic test (IWC-5222) of Class 2 pressure retaining piping each inspection interval.
Paragraph IWC-5222(a) requires that the system hydrostatic test pressure be at least
- 1. 10 times the system pressure for systems with Design Temperature of 200'F or less, and at least 1.25 times the system pressure for systems with Design Temperature above 200'F.
The system pressure shall be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.
Licensee's Code Relief Re uest:
Relief is requested from performing the Code-required pressure test of the Class 2 non-safety related system containment penetration piping listed below.
Licensee's Pro osed Alternative Examination:
The Licensee states
- that, for all of the subject lines, a local leak rate test (LLRT) at 50 psig will be performed per 10 CFR 50 Appendix J every 3 I/3 years.
If excessive leakage is discovered during the LLRT, additional testing will be performed as necessary to identify the location of the leakage.
This testing may be visual examination following application of leak detection fluid, extension of the test boundary to eliminate boundary valve leakage, use of ultrasonic leak detection equipment to detect valve seat
- leakage, or other means.
Appropriate repairs in accordance with ASHE Section XI requirements will be made, and the LLRT will be reperformed until successful test results are obtained.
Type "C" local leak rate testing methods are similar to those described in ASHE Section XI IWV-3424 except that the method,
- pressure, Acceptance
- Criteria, and schedule are specified and are in more detail.
Paragraph IWV-3424, "Seat Leakage Measurement,"
states that valve seat leakage may be determined by one of the following:
(a) draining the line, closing the valve, bringing one side to test pressure, and measuring leakage through a downstream tell-tale connection, or (b) by measuring the feed rate required to maintain pressure between two valves or between two seats of a gate valve, provided the total apparent leak rate is charged to the valve or gate valve seat being tested, and that the conditions required by IWV-3423 (valve pressure test direction and exceptions) are satisfied.
LLRT is an instrumented test measuring leakage throughout the entire test boundary, including the penetration valves and the pipe segment inside the penetration itself.
The VT-2 examination checks only the accessible outside surface of the pipe (or floors underneath) for evidence of leakage that is visually apparent.
In addition to performing the Appendix J LLRT tests at least once every 3 I/3 years, a VT-2 examination will be performed during a system functional test at normal operating pressure once each 10 years for lines
- 1679, 3001,
- 3729, 1161,
- 3000, 531,
- 986, 527,
- 3242, and 4353.
Licensee's Basis for Re uestin Relief:
The Licensee states that the components,
- piping, and valves associated with these containment penetrations are classified as Code Class 2 solely on the basis that they are required to ensure containment integrity.
They have no other safety related function.
These lines can be considered in the three categories, discussed below.
The following lines operate at 50 psig or less:
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Com onent or Pi in S stem Descri tion P2R quench Tk Gas Analyzer Rv's Discharge to P.R.T.
React Cool Drn Tk Vent React Cool Drn Tk Gas Anal Chps Air Sup Fans 1
8 2 Disch Ext and Penetrator 83 Inlet 5 Air Sup Chps Exh Air Filt 2 Inlet Chps Exh Sys Flow Cont In Containment Vacuum Relief Containment Purge Relief Containment Purge In Incore Chiller Water Rtn Incore Chiller Water Supply Containment Air Sample Inlet Containment Air Sample Return Post LOCA Samp Cnt Air Rtn Post LOCA Samp Cnt Air Sup Hyd Mon Cel 82 Cnt 'Air Sup Hyd Mon Cel 82 Cnt Air Rtn Hyd Mon Cel 83 Cnt Air Sup Hyd Mon Cel 83 Cnt Air Rtn Line Number s
1163
- 1459, 2003,
- 2004, 2061,
- 2518, 2572,
- 2998, 2999,
- 3851, 3852 525 526
- 4382, 4386,
- 4387, 4388, 4389 4390 4395 647 K2-48" (RCV-11 to RCV-12)
K2-48" (FCV-661 to FCV-660) 3936 3937 3837 3838 5190 S-3/8" (FCV-698 to FCV-699) 4633 4634 4635 4636 The Licensee states that -the scheduled Appendix J LLRT tests at 50 psig, which are conducted at least once every 3 1/3 years, fully demonstrate all aspects of the safety related containment integrity function of the component.
The Licensee requests to substitute the LLRT for the VT-2 examination in these cases.
The following lines are not normally in service but may see operational pressures greater than 50 psig during the occasions they are in use:
Com onent or Pi in S stem Descri tion Accums Samples Hdr Aux Steam Cont Penetrator Cont Str Sumps Pps Disch Refueling Canal Water Inlet Refueling Canal Water Return Post LOCA Sample 8
R E Cavity Sump React Cool Drn Pps Disch Hdr Service Air Penetrator Hdr Line Number 1679 3935 749 3001 2993 4663 3729 3941 Fluid Wtr Stm Wtr Wtr Wtr Wtr Wtr Air 650 105 27 70 7
<50 80 100 650 110 63 130 54 80 145 130 Norm.
Max.
Press.
Press.
~s~i Qsicri These lines would nominally be required to have a system functional test at normal operating pressure once each 3 1/3 years.
The concern is that since these lines can see pressures greater than 50 psig, a leak may
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develop at this higher pressure which would subsequently degrade the containment integrity function.
For lines 1679,
- 3001, and 3729, which also receive the Appendix J LLRT tests at least once every 3 1/3 years, the Licensee believes that a VT-2 examination during a system functional test once each 10 years adequately demonstrates system integrity at the higher operating pressure, while maintaining the plant ALARA goals.
The
- Licensee, therefore, requests that the time period of the system functional test for these lines be increased from 3 1/3 years to 10 years.
The remaining lines in this category (3935,
- 749, 2993,
- 4663, 3941) should be tested with the Appendix J LLRT each 3 1/3 years.
The specific reasons for which the Licensee requests to substitute LLRT for periodic system functional tests follow:
Line 3935:
This line is isolated during all operating modes and has never been in operation.
Any existing leaks would be identified by LLRT and the line's integrity would not be challenged by system pressure until the next test.
Line 749 (Unit 1):
This line is seldom operated
- and, when in service, normally sees only 27 psig, although the design maximum is 63 psig.
The LLRT at 50 psig guarantees line integrity at nearly double its normal pressure.
Line 749 (Unit 2):
This line is seldom operated
- and, when in service, normally sees only 33 psig, a>though the design maximum is 67 psig.
The LLRT at 50 psig guarantees line integrity at nearly double its normal pressure.
Line 2993 (Unit 1):
This line operates only in mode 6, and its normal pressure is only 7 psig, although the design maximum is 54 psig.
The LLRT at 50 psig guarantees its integrity at over seven times its normal pressure.
Line 2993 (Unit 2):
This line operates only in mode 6, and its normal pressure is only 18 psig, although the design maximum is 47 psig.
The LLRT at 50 psig guarantees its integrity at nearly three times its normal pressure.
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'L il Line 4663:
This system normally operates at less than 50 psig, although the design maximum is 80 psig.
Again the LLRT assures line integrity, and the Code examination would be based on the lower normal operating pressure.
Line 3941:
This line is not in service in modes 1 through 4 and has strict administrative controls for its use.
Containment integrity is not applicable when operating in modes 5 and 6.
A pressure test using water could cause the following problems:
(a) potential plant trip due to moisture in instrument air lines if any water leaks by or remains in the lines, (b) water in the supply air to safety related equipment thereby damaging components, and (c) water in the service air line which could cause corrosion.
The LLRT is as effective for this system as the VT-2 examination, considering the limitations to VT-2 and normally isolated condition of the line.
The following lines are normally in service at a pressure greater than 50 psig:
Com onent or Pi in S stem Oescri tion PZR Relief Tk Nq Supply Pri Wtr Sup to Pzr Relief Tk Tanks N2 Supply Hdr Firewater Supply Before Cont.
React Cool Drn Tk N2 Supply Inside Cnt Instr Air Sup Hdr Cnt Instr Air Sup FCV-584 BP Line
/umber 1161 3000 531 986 527 3242 4353 Norm.
Hax.
Press.
Press.
F1 ui d
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~s~i Ns 108 150 Wtr 128 140 Ny 900 1000 WKr 151 210 N2 108 165 Asr 100 110 Air 100 110 These lines would nominally be required to have a hydrostatic test at
- 1. 1 times the relief valve set point for that portion of the system once each 10 years.
,Since all of the lines in this category are supply lines into containment, failure of these systems could result in (a) leakage of the process fluid/gas into containment due to the greater system pressure than containment maximum pressure, or (b) leakage of the process fluid outside containment, again due to the greater system pressure.
Neither of these conditions would result in containment leakage to the environment.
Also, since the maximum pressure required for the safety related containment integrity function is less than
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50 psig, the normal system pressure effectively constitutes a
hydrostatic test for these lines.
Furthermore, these lines again receive the Appendix J LLRT tests at least once each 3 1/3 years.
The
- Licensee, therefore, requests 'that the system pressure requirement for these lines be reduced from 1. 1 times the relief valve set point to the normal operating pressure of the system.
Additionally, for line 531, a pneumatic hydrostatic test at 1100 psig (RV-290 set point is 1000 psig) would create the potential for serious injury to examination personnel.
Since the line is continuously pressurized with 900 psig nitrogen, leakage would be continuously noticeable due to loss of inventory.
Staff Evaluation and
Conclusions:
The intent of the Code is being met by performance of the Licensee's proposed alternative tests in most cases.
In these
- cases, the lines will be tested at a higher pressure than required by the Code.
In the case of lines
- 1679, 3001,
- 3729, and 3935, which are not normally in service but may see operational pressures greater than 50 psig 'during the occasions they are in use, the impracticality of performing the required system functional test each inspection period has not been demonstrated.
The fact that these lines are not normally in service and that line 3935 has not yet been used is not justification for granting relief.
The impracticality of performing a pressure test of line 3941 has not been demonstrated.
The Licensee's concern is that 'a pressure test using water could cause problems since this is an air containing line.
This is not a valid concern based on Paragraph IWC-5210(b) of Section XI of the Code.
Paragraph IWC-5210(b) states, in part, that the contained fluid in the system shall serve as the pressurizing
- medium, except that in steam systems either water or air may be used.
Where air is used, the test procedure shall permit the detection and location of through-wall leakages in components of the system tested.
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th For lines 527, 986,'1161,
- 3000, 3242, and 4353, which are normally in service at a pressure greater than 50 psig, relief is requested from performing the Code-required pressure test based on the fact that the failure of these lines would not result in containment leakage to the environment and that the maximum pressure required for the safety related containment integrity function is less than 50 psig.
The Licensee has not demonstrated the technical impracticality of performing the Code-required pressure tests.
In the case of line 531, which is continuously pressurized with 900 psig nitrogen, the staff concurs with the Licensee that a pneumatic test at 1100 psig could be potentially hazardous to examination personnel.
Based on the above evaluation, relief is granted as requested for all lines listed above except for lines 527,
- 986, 1161,
- 1679, 3000,
- 3001, 3242,
- 3729, 3935, and 4353 for which relief is denied.
G.
Re vest for Relief 9 Units 1
and 2
S stem Pressure Test of Class 2
Non-Safet Related Fuel Transfer Tube to Refuelin Canal Code Re uirement:
Section XI, Table IWC-2500-1, Examination Category C-H, Item C7.20 requires a 10Ã visual (VT-2) examination during a system functional test (IWC-5221) of Class 2 pressure retaining piping each inspection period.
Paragraph IWC-5221(a) states that the nominal operating pressure of the system functional test shall be acceptable as the system test pressure.
Licensee's Code Relief Re uest:
Relief is requested from performing the Code-required pressure test of the Class 2 Fuel Transfer Tube to the Refueling Canal (line No. 1336).
icensee's Pro osed Alternative Examination:
The Licensee states that the integrity of the 0-ring seal at the flange will be tested every 3 1/3 years.
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'I III icensee's Basis for Re uestin Relief:
The Licensee states that the refueling fuel transfer tube is inaccessible as it is encased in concrete.
Staff Evaluation and
Conclusions:
The Code-required pressure test of the fuel transfer tube to refueling canal is impractical to perform as the subject line is encased in concrete.
The Licensee's proposed alternative test of the integrity of the 0-ring seal at the flange is acceptable as it will provide reasonable assurance of the continued inservice structural integrity of this piping.
Therefore, relief is granted as requested.
III.
CONC LUS ION Paragraph 10 CFR 50.55a(g)(4) requires that components (including supports) which are classified as ASHE Code Class 1, 2, and 3 meet the requirements, except design and access provisions and preservice requirements, set forth in applicable editions of ASNE Section XI to the extent practical within the limitations of design,
- geometry, and materials of construction of the components.
Pursuant to 10 CFR 50.55a(g)(5)(iii), the Licensee determined that conformance with certain Code requirements is impractical for his facility and submitted supporting information.
The staff has reviewed the Licensee's submittals and has concluded that there are cases in which the requested relief cannot be granted due to insufficient justification and those where relief can be granted as requested.
In the case of Request for Relief 8 (Units 1 and 2), the Licensee has not provided sufficient justification for some of the lines listed; therefore, relief cannot be granted for those lines.
Pursuant to 10 CFR 50.55a(g)(6)(i),
the staff concludes that the requirements of the Code are impractical and relief may be granted for the issues described in Requests for Relief NDE-006, NDE-008, NDE-012, 8 (in part),
and 9 for Unit 1 and Requests for Relief NDE-007, NDE-009, NDE-015, 8 (in part),
and 9 for Unit 2 subject to the conditions described in this evaluation.
Such relief is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.
This relief has been granted giving due
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I consideration to the burden upon the Licensee that could result if the requirements were imposed on the facility.
The staff concludes that the Diablo Canyon Power Plant, Units 1 and 2, First Ten-Year Interval Inservice Inspection Program Plans, Revisions 7 and 4, respectively, with the information provided and the specific written relief, with the exception of Relief Request 8 (in part) (Units 1 and 2), constitute the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5. and are therefore acceptable.
Each of Tables 1 and 2
presents a summary of the reliefs requested and the status of the requests as determined by the staff for Units 1 and 2, respectively.
I 4
Diablo Canyon Nuclear Power Plant, Unit 1
Page 1 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF IS I PROGRAM Rel ief Request Number Item No.
Exam.
System or Cat.
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-001 81.11 8-A Reactor Pressure Vessel Circumferential Shell Weld 10-442 Volumetric Volumetric (UT) examination to extent practical Granted NDE-002 NDE-002 NDE-003 81.21 8-A 81.22 8-A 81.40 8-A Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Circumferential Head Welds:
4-443 6-4468 Meridional Head Welds:
1-443A through F
1-446A through F
Head-To-Flange Meld 6-446A Volumetric Volumetric Volumetric None Volumetric (UT) examination to extent practical Volumetric (UT) examination to extent practical Granted Granted Granted NDE-004 83.90 B-D Reactor Pressure Vessel Nozzle-To-Vessel Melds:
29-inch Outlet Nozzles (Total 4) 27.5-inch Inlet Nozzles (Total 4)
Volumetric Volumetric (UT) examination to extent practical Granted NDE-008A 85.20/
8-F Pressurizer 85.50 NDE-012A 83.120 B-D Pressurizer Nozzle-To-Safe End Welds:
WIB-71SE WIB-322SE Nozzle Inside Radiused Sections:
Safety Nozzle, Spray Nozzle, Surge Nozzle, and Relief Nozzles (3)
Volumetric and Surface Volumetric Surface and Volumetric (UT) examinations to extent practical None Granted Granted
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Diablo Canyon Nuclear Power Plant, Unit 1
Page 2 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF ISI PROGRAM Relief Request Number NDE-0088 Item No.
85.30/
85.50 Exam.
System or Cat.
~Con anent 8-F Steam Generator Volume or Area to be Examined Nozzle-To-Safe End Welds:
MIB-RC-2-6SE WIB-RC-3-5SE WIB-RC-4-5SE WI8-RC-1-6SE WIB-RC-2-7SE WIB-RC-3-6SE WIB-RC-4-6SE Required Method Volumetric and Surface Licensee Proposed Alternative 100/ Surface examination and Volumetric (UT) examination to extent practical Relief Request Status Granted NDE-008C(*) 89.11 8-J Piping Welds:
WIB-RC-1-12 WIB-RC-1-13 WIB-RC-2-5 WI8-RC-2-9 WIB-RC-2-10 WI8-RC-2-14 MI8-RC-2-15 WIB-RC-3-12 WIB-RC-3-13 MI8-RC-4-12 WIB-RC-4-13 WIB-1 WIB-5 WIB-16 WIB-64 WIB-67 WIB-68 WIB-82 WIB-83 WIB-151 WI8-171(*)
WIB-175 WIB-210 MIB-248 WIB-267 WIB-276(*)
MIB-289 WI8-313SE(*)
WI8-319 WIB-321 WIB-334 WIB-361 WIB-383 WIB-400 WIB-401 WIB-408 WIB-4158(*)
WIB-416A(*)
WI8-417 WIB-422 WIB-4328(*)
WIB-433A(*)
WIB-433 WIB-442 WI8-444 Volumetric and Surface Surface and Granted Volumetric (UT) examinations to extent practical
e I'
V 4
Diablo Canyon Nuclear Power Plant, Unit 1
Page 3 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF ISI PROGRAM Relief Request Item Exam.
System or Number No.
Cat.
~tom onent NDE-008C(*) B9.21 B-J Piping NDE-008C B9.31 B-J Piping NDE-0128(*) B3.140 B-D Steam Generator Volume or Area to be Examined Meld WIB-124(*)
WIB-RC-2-11 WIB-RC-2-12 MIB-RC-2-16 WIB-RC-2-18BC Nozzle Inside Radiused Sections:
Primary Inlet and Outlet Nozzles Required Method Surface Volumetric and Surface Volumetric Licensee Proposed Alternative Surface examination to extent practical 100% Surface examination and Volumetric (UT) examination to extent practical None Relief Request Status Granted Granted Granted(**)
NDE-006A(*) C1.10 and C1.20 C-A Seal Injection Filter 1-1 Girth Welds G-A and G-B Volumetric None Granted(**)
NDE-006A(*) C1.10 and C1.20 NDE-006A(*) C1.10 and C1.20 C-A Excess Letdown Heat Exchanger C-A RHR Heat Exchangers 1-1 and 1-2 Girth Welds G-A and G-B Girth Welds G-A and G-D Volumetric Volumetric Surface and volumetric(*)
examinations to extent practical Surface and volumetric(*)
examinations to extent practical Granted(**)
Granted(**)
NDE-006A C1.20 C-A Stabilizer Girth Welds A and B
Separator Volumetric Volumetric (UT)
Granted examination to extent practical
~
I r
I" II
Diablo Canyon Nuclear Power Plant, Unit 1
Page 4 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF ISI PROGRAM Rel ief Request Item Exam.
System or Number No.
Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-006A(*) C2.20 C-B RHR Heat Exchangers 1-1 and 1-2 Nozzle-To-Shell Welds:
N-1 and N-2 Volumetric and Surface Surface and volumetric(*)
examination to extent practical Granted(**)
a NDE-007 C1.10 C-A Steam Circumferential Shell Welds:
Generator 1-3, 2-4, and 3-5 Volumetric Volumetric (UT) examination to extent practical Granted NDE-007 C1.20 C-A Steam Circumferential Head Weld Generator 4-7 Volumetric Volumetric (UT) examination to extent practical Granted NDE-007 C1.20 C-A Boron Circumferential Head Welds:
Injection A and B
Tank Volumetric Volumetric (UT) examination to extent practical Granted NDE-006B C1.20 C-A Regenerative Circumferential Head Welds:
Heat 9 and 12 Exchanger Volumetric 100/ Surface (PT)
Granted (aNa) examination NDE-006B C1.30 C-A Regenerative Tubesheet-To-Shell Welds:
Heat 10 and 11 Exchanger Volumetric Composite Surface (PT) examination of accessible areas of Welds 2, 3, 6, 7, 10, and 11 Granted
I
Diablo Canyon Nuclear Power Plant, Unit 1
Page 5 of 9 TABLE 1
SUMMARY
OF RELIFF RF.
UESTS IN REVISION 7 OF ISI PROGRAM Relief Request Number Item No.
Exam.
System or Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-011 C1.20/
C-A Regenerative Circumferential Head and C1.30 Heat Tubesheet-To-Shell Welds Exchanger Withdrawn ~
by License Incorporated into Relief Request NDE-006 NDE-008D C3.40 C-C Piping NDE-008D C5. 11 C-F Piping Integrally Welded Attachment Surface 74-29A Circumferential Weld WIC-27 Surface Surface (PT) examination to extent practical Surface (PT) examination to extent practical Granted Granted NDE-008D(*) C5.21 C-F Piping NDE-009 C4.30 C-D Safety Injection Pumps Circumferential Welds:
WIC-9-1(*)
MIC-348 MIC-184 WIC-353 MIC-249 MIC-101AI-4 WIC-289 MIC-1357E Bolting Volumetric and Surface Volumetric examination distributed over interval in accordance with Table IWC-2412-1 100% Surface examination and Volumetric examination to extent practical 100% Volumetric examination scheduled in accordance with plant maintenance schedule (once during interval)
Granted Granted
I
~
Diablo Canyon Nuclear Power Plant, Unit 1
Page 6 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF IS I PROGRAH Relief Request Number Item No.
Exam.
System or Cat.
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-010 1A 2A(*)
3 (*)
C6.10 C-G Centrifugal Suction End Plate Weld Charging Pump Hydrostatic Test of Class 2 Centrifugal Type Pumps and Associated Piping Hydrostatic Test of Class 2 Component Cooling Water Systems Hydrostatic Test of Class 2 Component Cooling Water Piping Associated with Containment Penetrations Surface examination distributed over interval in accordance with Table IWC-2412-1 IWC-5000 100/ Surface examination scheduled in accordance with plant maintenance schedule (once during interval)
Hydrostatic pressure boundary in accordance with IWA-5224(d) of 1980 Edition, 1981 Addenda at normal operating conditions Granted Granted Withdrawn Licensee(**)
(Previously denied in 12/14/88 SER)
Withdrawn by Licensee(**)
(Previously denied in 12/14/88 SER)
~
~
I
Diablo Canyon Nuclear Power Plant, Unit 1
Page 7 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF ISI PROGRAM Relief Request Number Item No.
Exam.
Cat.
System or
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status Hydrostatic Test of Class 2 Safety Injection, Residual Heat Removal, Reactor.
Coolant Pump Seal Injection, Charging and Boron Injection Piping Hydrostatic Test of Class 2 Reactor Coolant Pump Seal Return Piping Hydrostatic Test of Class 2
RHR Pump Suction Piping from Containment Sumps IWC-5222 IMC-5000 IMC-5000 Portions not isolatable from Class 1 tested to Class 1
requirements None None Granted Granted Granted 8(*)
Pressure Test of Class 2 Non-Safety Related System Containment Penetrati Lines 525,
- 526, 527,
- 531, 647,
- 749, 1161,
- 1163, 1459,
- 1679, 2003,
- 2004, 2518,
- 2572, 2993,
- 2998, 2999,
- 3000, 3242,
- 3729, 3837,
- 3838, 3851,
- 3852, 3936,
- 3937, 3941,
- 4353, 4382,
- 4386, 4388e 4389~
4390a 4395 4633a 4634a
- 4636, 4663,
- 5190, K2-48" (RCV-ll to K2-48" (FCV-661 to FCV-660), S-3/8" (FCV-698 to FCV-699) ons:
- 986, 2061,
- 3001, 3935,
- 4387, 4635, RCV-12),
IMC-5221/
IMC-5222 Local leak rate test at 50 psig performed per 10 CFR 50 Appendix J every 3 1/3 years.
VT-2 examination during functional test at normal operating pressure every 10 years for lines 527,
- 531, 986,
- 1161, 1679,
- 3000, 3001,
- 3242, 3729, and 4353 Denied(**)
for lines
- 527, 986,
- 1161, 1679,
- 3000, 3001,
- 3242, 3729,
'and 4353; Granted(**)
for all other lines listed
Diablo Canyon Nuclear Power Plant, Unit 1
Page 8 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF IS I PROGRAM Relief Request Number Item Exam.
System or No.
Cat.
~Com anent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status 9 (*)
1B 2B(*)
Pressure Test of Class 2 Non-Safety Related Fuel Transfer Tube to Refueling Canal (Line 1336)
Hydrostatic Test of Class 3 Centrifugal Type Pumps and Associated Piping Hydrostatic Test of Class 3 Component Cooling Water Systems Hydrostatic Test of Embedded Class 3
Auxiliary Saltwater Piping IWC-5221 IWD-5000 IWD-5000 Integrity of the 0-ring seal at the:flange will be tested every 3 1/3 years Hydrostatic pressure boundary in accordance with IWA-5224(d) of 1980 Edition, 1981 Addenda at normal operating conditions Periodic pump testing to verify unimpaired flow through inaccessible portions and visual leak test of exposed portions during system pressure tests Granted(**+
Granted Withdrawn by Licensee(*~
(Previouslj denied in 12/14/88 SER)
Granted
~
~
't
~
~
~
Diablo Canyon Nuclear Power Plant, Unit 1
Page 9 of 9 TABLE 1
SUMMARY
OF RELIEF RE UESTS IN REVISION 7 OF ISI PROGRAM Relief Request Number Item No.
Exam.
System or Cat.
~Coo onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status NDE-005 REP-001 Exemption Criteria for Pressure Retaining Welds in Class 2 Piping Repair and Replacement of Class 3 Diesel Engine Blocks IWC-1220 of 1974 Edition, Summer 1975 Addenda IWC-1220 of 1977
- Edition, Summer 1978 Addenda Granted Withdrawn by Licensee
(*)
Revised per Revision 7 of ISI Program.
(**)
New or revised status of relief request.
I h
Diablo Canyon Nuclear Power Plant, Unit 2 Page 1 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Relief Request Number Item No.
Exam.
System or Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status NDE-001 81.11 8-A Reactor Pressure Vessel Circumferential Shell Meld 10-201 Volumetric Volumetric (UT) examination to extent practical Granted NDE-002 81.21 8-A Reactor Pressure Vessel Circumferential Head Welds:
4-202 6-2058 Volumetric None Granted NDE-002 NDE-003 a
NDE-004 81.22 8-A 81.40 8-A 83.90 8-D Reactor Pressure Vessel Reactor Pressure Vessel Reactor Pressure Vessel Heridional Head Welds:
1-202A through F
1-205A through F
Head-To-Flange Meld 6-205A Nozzle-To-Vessel Melds:
29-inch Outlet Nozzles (Total 4) 27.5-inch Inlet Nozzles (Total 4)
Volumetric Volumetric Volumetr ic Volumetric (UT) examination to extent practical Volumetric (UT) examination to extent practical Volumetric (UT) examination to extent practical Granted Granted Granted NDE-005 83.110 8-D Pressurizer Nozzle-To-Vessel Melds:
Safety Nozzle, Spray Nozzle, Relief Nozzles (3),
and Surge Nozzle Volumetric Volumetric (UT)
Granted examinations to extent practical NDF.-005 83.120 8-D Pressurizer Nozzle Inside Radiused Sections:
Safety Nozzle, Spray Nozzle, Surge Nozzle, and Relief Nozzles (3)
Volumetric None Granted
Diablo Canyon Nuclear Power Plant, Unit 2 Page 2 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF IS I PROGRAM Relief Request Item Number No.
NDE-009E(*) B5.10/
B5.50 Exam.
System or Cat.
~Com anent B-F Reactor Pressure Vessel Volume or Area to be Examined Nozzle-To-Safe End Welds:
MIB-RC-1-1SE MIB-RC-2-1SE Required Method Volumetric and Surface Licensee Proposed Alternative 100% Surface examination and Volumetric (UT) examination to extent practical
- Relief, Request Status Granted(**
NDE-009A(*) B5.20/
B-F B5.50 NDE-009B B5.30/
B-F B5.50 Pressurizer Steam Generator Nozzle-To-Safe MIB-359SE WIB-369SE WIB-380SE WIB-423SE(*)
Nozzle-To-Safe WIB-RC-1-5SE MIB-RC-2-5SE WIB-RC-3-5SE MIB-RC-4-5SE End Welds:
End Welds:
WI8-RC-1-6SE MIB-RC-2-6SE WIB-RC-3-6SE WIB-RC-4-6SE Volumetric and Surface Volumetric and Surface 100% Surface examination and Volumetric (UT) examination to extent practical 100% Surface examination and Volumetric (UT) examination to extent practical Granted Granted NDE-009C B9.12 B-J Piping Welds:
WIB-RC-2-8LS-A WIB-RC-2-8LS-B Volumetric and Surface 100% Surface examination and Volumetric (UT) examination to extent practical Granted
s I
(
Diablo Canyon Nuclear Power Plant, Unit 2 Page 3 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Relief Request Item Exam.
System or Number No.
Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-009C(*) B9.11 B-J Piping NDE-009C(*) B9.21 B-J Piping Welds:
MI8-RC-1-2(*)
MIB-RC-l-ll MIB-RC-1-12 WIB-RC-2-2(*)
WIB-RC-2-11 MIB-RC-2-12 WIB-RC-2-15 WIB-RC-3-11 WIB-RC-3-12 WIB-RC-4-11 WIB-RC-4-12 WIB-6(*)
MIB-11 WIB-15 MIB-39(*)
WIB-47 WIB-56 WIB-62 MIB-71 MIB-88(*)
WIB-92 WIB-97 WIB-106 Wel ds:
WIB-408 MI8-410A WI8-119 WIB-164 WIB-172 WIB-177 WIB-181 WIB-196 WIB-197(*)
WIB-203 WIB-243 WIB-246 (*)
WIB-253 WIB-265 WIB-291(*)
MIB-299 MIB-300 MI8-322(*)
WIB-362 WIB-374 MIB-378 WIB-391 MIB-429 MIB-430 WI8-514 MI8-856 Volumetric and Surface Surface Surface and Volumetric (UT) examinations to extent practical Surface examination to extent practical Granted Granted(**)
I.
'4 t
Diablo Canyon Nuclear Power Plant, Unit 2 Page 4 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Rel ief Request Item Exam.
System or Number No.
Cat.
~Com onent NDE-009C(*) B9.31 B-J Piping NDE-009C(*) B10.10 B-K-I Piping NDE-015(*)
B3.140 B-D Steam Generator Volume or Area to be Examined Welds:
WI8-1 WIB-104 WIB-37(*)
WIB-192 WIB-55(*)
Integral Attachment Melds:
409-3A 989-29R 898-2 Nozzle Inside Radiused Sections:
Primary Inlet and Outlet Nozzles Required Method Volumetric and Surface Surface Volumetric Licensee Proposed Alternative 100% Surface examination and Volumetric (UT) examination to extent practical Surface examination to extent practical None Rel ief Request Status Granted Granted(**)
Granted(**)
NDE-007A(*) C1.10 and C1.20 C-A Seal Injection Filter 2-1 Girth Melds 1 and 2
Volumetric None Granted(**)
NDE-007A(*) C1.10 and C1.20 NDE-007A(*) C1.10 and C1.20 C-A Excess Letdown Heat Exchanger C-A RHR Heat Exchanger 2-1 Girth Welds 13 and 14 Girth Melds 21 and 22 Volumetric Volumetri c Surface and volumetric(*)
examinations to extent practical Surface and volumetric(*)
examination to extent practical Granted(**)
Granted(**)
'I
~'
4
Diablo Canyon Nuclear Power Plant, Unit 2 Page 5 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Relief Request Number Item No.
Exam.
System or Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Rel ief Request Status NDE-007A Cl.20 C-A Stabilizer Girth Welds G-A and G-B Separator Volumetric Volumetric (UT) examination to extent practical Granted NDE-007A(*) C2.20 C-B RHR Heat Nozzle-To-Shell Welds:
Exchanger 23 and 24 2-1 Volumetric and Surface Surface and volumetnc(*)
examination to extent practical Granted(**)
NDE-008 C1.20 C-A Boron Circumferential Head Welds:
Injection A and B
Tank Volumetric Volumetric (UT) examination to extent practical Granted NDE-007B C1.20 C-A Regenerative Circumferential Head Welds:
Heat 9 and 12 Exchanger Volumetric 1001. Surface (PT)
Granted examination NDE-007B C1.30 C-A Regenerative Tubesheet-To-Shell Welds:
Heat 10 and 11 Exchanger Volumetric Composite Surface (PT) examination of accessible areas of Welds 2, 3, 6, 7, 10, and 11 Granted 0
I C
~\\ r 4
7 4
Diablo Canyon Nuclear Power Plant, Unit 2 Page 6 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Relief Request Number Item Exam.
System or No.
Cat.
~Com ohaot Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status NDE-013 Cl.20/
C-A Regenerative Circumferential Head and C1.30 Heat Tubesheet-To-Shell Welds Exchanger Withdrawn ~
by License~
Incorporated into Relief Request NDE-007 NDE-009D C5. 11 C-F Piping Circumferential Meld WIC-36 Surface Surface (PT) examination to extent practical Granted NDE-009D(*) C5.21 C-F Piping Circumferential Welds:
WIC-90 WIC-1357A(*)
WIC-105 WIC-1357B(*)
WIC-332 WIC-1357C(*)
WIC-325 WIG-1357E(*)
MICG-103-1 Volumetric 100% Surface and Surface examination and Volumetric (UT) examination to extent practical Granted NDE-009F(*) C3.40 C-C Valve NDE-010 C4.30 C-D Safety Injection Pumps Integral Attachment Meld:
23-36R Bolting Surface Volumetric examination distributed over'interval in accordance with Table IWC-2412-1 Surface examination to extent practical 100% Volumetric examination scheduled in accordance with plant maintenance schedule (once during interval)
'Granted(**)
Granted
r I~
fa
Diablo Canyon Nuclear Power Plant, Unit 2 Page 7 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Relief Request Number Item Exam.
System or Mo.
Cat.
~Com onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status NDE-Oll 1A 2A(*)
3 (*)
C6. 10 C-G Centrifugal Suction End Plate Meld Charging Pump Hydrostatic Test of Class 2 Centrifugal Type Pumps and Associated Piping Hydrostatic Test of Class 2 Component Cooling Mater Systems Hydrostatic Test of Class 2 Component Cooling Water Piping Associated with Containment Penetrations Surface examination distributed over interval in accordance with Table IWC-2412-1 IWC-5000 IOOX Surface examination scheduled in accordance with plant maintenance schedule (once during interval)
Hydrostatic pressure boundary in accordance with IWA-5224(d) of 1980 Edition, 1981 Addenda at normal operating conditions Granted Granted Mithdrawn Licensee(**)
(Previously denied in 12/14/88 SER)
Withdrawn by Licensee(**)
(Previously denied in 12/14/88 SER)
0
~ I
Diablo Canyon Nuclear Power Plant, Unit 2 Page 8 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Rel ief Request Number Item No.
Exam.
Cat.
System or
~Com anent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status 8(*)
Hydrostatic Test of Class 2 Safety Injection, Residual Heat Removal, Reactor Coolant Pump Seal Injection, Charging and Boron Injection Piping Hydrostatic Test of Class 2 Reactor Coolant -Pump Seal Return Piping Hydrostatic Test of Class 2
RHR Pump Suction Piping from Containment Sumps Pressure Test of Class 2 Non-Safety Related System Containment Penetrations:
Lines 525,
- 526, 527,
- 531, 647,
- 749, 986,
- 1161, 1163,
- 1459, 1679,
- 2003, 2004,
- 2061, 2518 j 2572 a
2993 a
2998 2999 a 3000 3001
~
- 3242, 3729,
- 3837, 3838,
- 3851, 3852,
- 3935, 3936,
- 3937, 3941,
- 4353, 4382,
- 4386, 4387,
- 4388, 4389,
- 4390, 4395,
- 4633, 4634,
- 4635, 4636,
- 4663, 5190, K2-48" (RCV-11 to RCV-12),
K2-48" (FCV-661 to FCV-660), S-3/8" (FCV-698 to FCV-699)
IWC-5222 IWC-5000 IWC-5000 IWC-5221/
IWC-5222 Portions not isolatable from Class 1 tested to Class 1
requirements None None Local leak rate test at 50 psig performed per 10 CFR 50 Appendix J every 3 1/3 years.
VT-2 examination during functional test at normal operating pressure every 10 years for lines 527,
- 531, 986,
- 1161, 1679,
- 3000, 3001,
- 3242, 3729, and 4353 Granted Granted Granted Denied(**)
for lines
- 527, 986,
- 1161, 1679,
- 3000, 3001, ~
- 3242, 3729, QP and 4353; Granted(**)
for all other lines listed
i)I II
Diablo Canyon Nuclear Power Plant, Unit 2 Page 9 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM Rel ief Request Number Item Exam.
System or No.
Cat.
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status 9(*)
1B 2B(*)
Pressure Test of Class 2 Non-Safety Related Fuel Transfer Tube to Refueling Canal (Line 1336)
Hydrostatic Test of Class 3 Centrifugal Type Pumps and Associated Piping Hydrostatic Test of Class 3 Component Cooling Water Systems Hydrostatic Test of Embedded Class 3
Auxiliary Saltwater Piping IWC-5221 IWD-5000 IWD-5000 Integrity of the 0-ring seal at the flange will be tested every 3 1/3 years Hydrostatic pressure boundary in accordance with IWA-5224(d) of 1980 Edition, 1981 Addenda at normal operating conditions Periodic pump testing to verify unimpaired flow through inaccessible portions and visual leak-test of exposed portions during system pressure tests Granted(*n Granted Withdrawn by Licensee(* ~
(Previousl~
denied in 12/14/88 SER)
Granted
- c. 0~ -.i I ~
Diablo Canyon Nuclear Power Plant, Unit 2 Page 10 of 10 TABLE 2
SUMMARY
OF RELIEF RE UESTS IN REVISION 4 OF ISI PROGRAM far v
n Rel ief Request Number Item No.
Exam.
System or Cat.
~Con onent Volume or Area to be Examined Required Method Licensee Proposed Alternative Relief Request Status NDE-006 NDE-014 REP-001 Exemption Criteria for Pressure Retaining Welds in Class 2 Piping Exemption of Class 2 Components Repair and Replacement of Class 3 Diesel Engine Blocks IWC-1220 of 1974 Edition, Summer 1975 Addenda IMC-1220 of 1977 Granted
- Edition, Summer 1978 Addenda Withdrawn by Licensee Withdrawn by Licensee NDE-012 Scheduling of Class 2 Pipe Welds in Multiple Stream Systems IWC-2411 (Examinations divided among the multiple streams of a system)
Sample selected in one stream of "multiple stream" systems (100% of the Code-required total of welds will be examined)
Granted
(*)
Revised per Revision 4 of ISI Program.
(**)
New or revised status of relief request.
~ I l)