ML16148B006
| ML16148B006 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/14/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16148B005 | List: |
| References | |
| NUDOCS 9105230261 | |
| Download: ML16148B006 (12) | |
Text
S RE0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN DUKE POWER COMPANY DOCKET NOS. 50-269, 50-270 AND 50-287 OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3
- 1. INTRODUCTION Technical Specification 4.2.1 for the Oconee Nuclear Station, Units 1, 2, and 3, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME) 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 ASME 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).
10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used if (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the second ten-year interval comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the start of the 120-month inspection interval, subject to the limitations and modifica tions listed therein. The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.
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 its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will pDtR
-2 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 reqirements were imposed.
On December 2, 1983, the licensee, Duke.Power Company, requested the approval of a common ISI interval start date of April 1, 1984, for all three Oconee units. The ASME Code edition and addenda applicable for an inspection interval with a start date of April 1, 1984, would be the 1980 Edition, Winter 1981 Addenda. This request was approved by the NRC staff on November 7, 1984. Subsequent to this approval, the licensee submitted a request on January 23, 1986, to move the interval start date back by one month to March 1, 1984.
Based on the start date of March 1, 1984, the licensee has prepared the Oconee Nuclear Station, Units 1, 2, and 3, Second Ten-Year Interval Inservice Inspection (ISI) Program Plan to meet the requirements of the 1980 Edition, Winter 1980 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code, except that the extent of examination of Class 2 piping welds in the Residual Heat Removal, Emergency Core Cooling, and Containment Heat Removal systems has been determined by the 1974 Edition, Summer 1975 Addenda as required by 10 CFR 50.55a(b)(2)(iv)(A) and Category D-B examinations will be performed according to the 1980 Edition, Winter 1982 Addenda. Use of this later Code edition is acceptable provided all related requirements of the later addenda are met pursuant to 10 CFR 50.55a(g)(4)(iv).
The NRC staff, with technical assistance from its contractor, Science Applic ations International Corporation (SAIC), has evaluated the Second Ten-Year Interval Inservice Inspection Program Plan, additional information related to the Program Plan, and the requests for relief from certain ASME Code require-,
ments determined to be impractical or unnecessary for the Oconee Nuclear Station, Units 1, 2, and 3, during the second inspection interval.
2.0 EVALUATION The ISI Program Plan has been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with exam4nation and test requirements of Section XI, (c) acceptability of the examination sample, (d) compliance with prior ISI commitments made by the licensee, (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 Plan, with the exception of the denied relief requests, reflects compliance with the requirements listed above.
The licensee's January 23, 1986, request to move the interval start date back by one month to March 1, 1984 and, therefore, to use the 1980 Edition, Winter 1980 Addenda, of the ASME Section XI Code in lieu of the 1980 Edition, Winter 1981 Addenda, is acceptable as the differences in the subject codes are administrative in nature, with no substantive technical differences.
-3 The information provided by the licensee in support of requests for relief from impractical requirements has been evaluated and the bases for granting relief from those requirements are documented in SAIC's Technical Evaluation Report (TER) SAIC-88/1942. We concur with and adopt the findings and recommendations contained in the subject report. Table 1 of this Safety Evaluation presents a summary of the reliefs requested and the status of the requests as determined by the NRC staff.
3.0 CONCLUSI-ON The NRC staff concludes that the Oconee Nuclear Station, Units 1, 2, and 3, Second Ten-Year Interval Inservice Inspection Program Plan, with the additional information provided and the specific written relief, constitutes the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.2.1 and is therefore acceptable, with the exception of the denied relief requests. We have determined that certain requirements of Section XI of the ASME Code for which the licensee has requested relief are either impractical or unnecessary to perform at the Oconee Nuclear Station, and the alternate examinations specified in the licensee's submittals ensure an acceptable level of structural integrity of the subject components. The alternate methods of examination are acceptable as discussed in the TER and are imposed in lieu of the applicable Code requirements.
For these requirements, relief from the Code requirements is granted as requested, or with conditions as specified in Table 1, pursuant to 10 CFR 50.55a(a)(3)i, 50.55a(a)(3)ii, and 50.55a(g)(6)(i).
The specific section is identified in Table 1. This 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 given due consideration to the burden that could result if the requirements were imposed on the facility.
Dated:
Principal Contributors: G. Johnson L. Wiens
Oconee Nuclear Station, Units 1, 2, and 3 Page 1 of 9
TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Request System or Exam.
Item Volume or Area Required Licensee Number Component Cat.
No.
to be Examined Method Proposed Relief Request ONS001 Clas 1Alternative Status ONS-t1 Class I
-F 65.10 RPV core flood Volumetric Volumetric Granted with (Units.1, Piping nozzle-to-safe end welds and surface exmnto frm cdios (2 each unt)sr)c examination from conditions
)(2 each unit) examinations io (NOTES 1 and 7)
ONS-002 Class1 8-J 89.11 Four inlet and two outlet Volumetric Volumetric Granted with (Units 1, Piping nozzle-to-pipe welds in and surface examination from nti 2, and 3) the RC System examinations ID conditions examiatios 10(NOTES 1, 2 and 7)
ONS-003 Reactor UT calibration blocks for ferritic steel Cal. blocks UT Cal. block Denied (Units 1, Coolant main loop welds made from 40350 used for material of ferritic steel same nom.
RC piping welds diam. and wall thick.
ONS-004 Pressurizer UT calibration blocks for examination of Cal. blocks Use existi ng Denied (Units 1, and Steam Pressurizer and Steam Generator welds made from a calibration 2, and 3) Generator nozzle blocks dropout or material of same spec.,
product form, and heat treatment
Oconee Nuclear Station, Units 1, 2, and 3 Page 2 of 9 TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Request System or Exam.
Item Volume or Area Required Propose Relief Request N
c t Cat No.
to be Examined Mehod Alternative Status ONS-005 Reactor Class I piping between valves:
Hydrostatic Surface exam. of Granted (Units 1, Coolant IRC-4 & IRC-66 (SYS 50, ISO 41, Unit 2) test per welds between (NOTE 9) 2, and 3) System 2RC-4 & 2RC-66 (SYS 50, ISO 44, Unit 2)
IWB-5222 valves at or 3RC-4 & 3RV-67 (SYS 50, 1SO 45, Unit 3) near the end of the interval ONS-006 Class 2 C-F C5.11 Containment spray system Surface N
(Units 3, Piping piping welds from valves examination one Denied for 2, and 3)
BS-14 and BS-19 to spray the CS system nozzles, and reactor piping welds; building emergency sump Granted for piping welds to valves te or LP-19 and LP-20 the e
sump line welds embedded in concrete, with ONS-07 Rectorcondition (NOTE 9 and 10)
ONdS-007 Coator 8-L-1 812.10 Pump casing welds Volumetric Volumetric exam.
Granted NSd008 Pumps examination to maximum (NOTE 9) aNd -0 3)mp extent practical (Units 2 and 3) 8-L-2 812.20 Pump casing internal VT-3 visual VT-3 exam to surfaces examination maximum extent practical
Oconee Nuclear Station, Units 1, 2, and 3 Page 3 of 9 TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Licensee Request System or Exam.
Item Volume or Area Required Proposed Relief Request Number Comonent
-Cat.
No.
to be Examined Method Alternative Status 3.4.1.2 Pressure Class I repair welds Hydrostatic Surface Granted with of4TER2 Injectin associated with check test after examination of conditions of TER Injection valve ILP-46 (1-1/2 inch repairs the replacement (NOTE 3 (Unit 1)
System valve) socket welds and 8) 3.4.1.3 Pressure Class I repair welds Hydrostatic System Relief not of4TER3 Inrection associated with check test after functional test required of TER Injection valve 2LP-45 repairs during next cold (valve 2LP-45 (Unit 2)
System shutdown of replaced, see sufficient Section duration 3.4.1.5 of TER) 3.4.1.4 Pressure Class I repair welds Hydrostatic System Granted with of4TER4 Inrection associated with 4-inch test after functional test conditions of TER Injection check valve 2HP-188 repairs during next (NOTE 4 refueling outage and 8)
Section Low 3.4.1.5 Pressure Class1 and 2 repair Hydrostatic Penetrant Granted with of TER welds assoc. with check test after examination and conditions of TER injection valve LP-131 and gate repairs inservice leak (NOTE 5 (Units 1 System valves LP-132 and LP-133 test and 8) and 2)
Oconee Nuclear Station, Units 1, 2, and 3 Page 4 of 9 TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Licensee Request System Cr Exam.
Item Volume or Area Required Proposed Relief Request Number Cor one*t Cat.
No.
to be Examined Method Alternative Status Section Steam Class 2 Steam generator Hydrostatic Penetrant exam.
Granted with 3.4.2.1 Generator drain lines between test after and system conditions of TER Drain 3A OTSG and 3FDW-144 repairs pressure test (NOTE 5 (Unit 3)
Lines prior to startup and 7)
Section Main Steam Class 2 repair welds Hydrostatic 1ooY*
Granted with 3.4.2.2 associated with MS Power test after radiographic conditions of TER Operated valve 2MS-84 repairs exam. of welds (NOTE 6 (Unit 2) and 7) 3.4.2.3 Pressure Class 2 repair welds Hydrostatic 100%
Granted with of TRervice associated with LPSW test after radiographic conditions of TER Service valve 3LPSW-15 repairs exam. and system (NOTE 6 inservice test and 7)
Section Low Class 2 repair welds Hydrostatic System Denied 3.4.2.4 Pressure associated with 14-inch test after functional test of TER Injection gate valve 2LP-19 repairs during next refueling outage Section Feedwater Class 2 repair weld 308 Hydrostatic Radiographic and Granted with 3.4.2.5 System test after VT-2 visual conditions of TER repairs examinations (NOTE 6 (Unit 1) and 7),
Oconee Nuclear Station, Units 1, 2, and 3 Page 5 of 9 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Licensee Request System on Exam.
Item Volume or Area Required Proposed Relief Request Number Component
-atj
-No.
to be xamined Method Alternative Status Section Low Class 2 repair welds 31 Hydrostatic Radiographic and Granted with 3.4.2.6 Pressure and 32 associated with test after VT-? visual conditions of TER Service valve ILPSW-6 repairs examinations (NOTE 6 (Unit 1)
Water and 7)
System 3.4.2.7 Pressure Class 2 and 3 repair Hydrostatic Radiographic Granted with of TRevice welds associated with test after examination and conditions of TER Service valve I[PSW-15 repairs system inservice (NOTE 6 (Unit 1)
Water la etad7 System leak test and 7)
Section Feedwater Class 2 repair welds Hydrostatic Surface exam.
Granted with 3.4.2.8 System associated with test after and VT-2 visual conditions (Unit 1)lIFOF-209 an repairs exam. during hot (NOTE 5 tIFOW shutdown and 7)
Section Feedwater Class 2 repair welds 3.4.2.9 System glo tdwtwlsHydrostatic Surface Granted with of TER associated with test after examination and conditions (Unit 2)valves 2FDW-206, repairs system inservice (NOTE 5 2FDW-209, and 2FDW-144 test and 7)
Oconee Nuclear Station, Units 1, 2, and 3 Page 6 of 9 TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Request System O Exam.
Item Volume or Area Required Proposed Relief Request Number Componen Cat to be Examined Method Alternative Rlfeus Section Emergency Class 3 piping downstream System None Granted 3.4.3.1 Feedwater of valves FDW-372 and inservice (NOTE 9) of TER System FDW-382 test (Units Y, 2, and 3)
Section Reactor Pressure testing of the Boundary Visual Relief not 3.4.3.2 Building Class 3 reactor building for examination required of TER Hydrogen hdoe ug atpesr (Units 1, Purge Cart hdoe per 2, and 3).
IWA-5224(d)
Section Penetration Class 3 penetration room System None Granted, with 3.4.3.3 Room Cla t
tn rystem None c
of TER Ventilation ventilation system pressure O
(Units 1, System test (NOTE 2, and 3)
Section Purif.
Class 3 purification VT-2 visual Hydrostatically Granted of Demin.
demineralizer piping examination tested by (NOTE 9) of TER System during performing a (Units 3) hydrostatic pressure drop 2, and 3) test test
Oconee Nuclear Station, Units 1, 2, and 3 Page 7 of 9 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Request Systemo Exam.
Item Volume or Area Required Proposed Relief Request Numer; No.
to be Examined Method Alternative Status Section Emergency Class 3 Velan Model Hydrostatic Liquid penetrant Relief not 3.4.3.5 FW Pump WH-254B-2TY gate valve test after exam of welds required of TER Turbine IS043 (3/4-inch valve) repairs and system (Unit 1)
Steam inservice test Drain Section Emergency Class 3 suction line Hydrostatic Liquid penetrant Granted 3.4.3.6 FW Pump tie-in weld to the test after exam. of welds (NOTE 9)
(Unit 1)
Oil Cooler 78-inch condenser repairs and system circulating water line inservice test Pump Section Auxiliary Class 3 repair welds Hydrostatic Weld radiography Granted 3.4.3.7 Steam associated with auxiliary test after and a system (NOTE 9) of TER System steam check valve IAS-39 repairs inservice test (Unit I)
Section Main Steam Class 3 repair welds Hydrostatic Weld radiography Granted 3.4.3.8 System associated with main test after and a system (NOTE 9) of TER steam check valves 3MS-83 repairs inservice test (Unit 3) and 3MS-85 Section Spent Fuel Class 3 repair welds Hydrostatic System Granted 3.4.3.9 Cooling associated with valve test after functional test (NOTE 9) of Et System SF-65 repairs (Unit 1)
Oconee Nuclear Station, Units 1, 2, and 3 Page 8 of 9 TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Request Sseor Ea ItmVlLicensee Numer System p
r Exam.
Item Volume or Area Required Proposed Relief Request NbrOMonent
- Cat, N.
to be Examined Method Alternative Status Section Main Steam Class 3 repair welds Hydrostatic Weld radiography Granted 3.4.3.10 System associated with MS check test after and system (NOTE 9) of TER valves 2MS-83 and 2MS-85 repairs inservice test (Unit 2)
Section Start date and applicable Code for the second ten-year inspection interval:
Granted 3.5.3 of Relief is requested from the requirements of Paragraph IWA-2400(b) and from
.(NOTE 8)
TER 10 CFR 50.55a(g)(4)(ll).
Instead of beginning April 1, 1984, and anplying the 1980 (Units I,- Edition, Winter 1981 Addenda, as approved on November 7, 1984,tescn nevlwl 2, and 3) begin March 1, 1984 and the 1980 Edition, Winter 1980 Addenda will be applied.
Section Snubbers Inservice testing requirements (snubber Articles Hydraulic and Denied 3.6.1 of functional testing program)
IWF-5300 mechanical TER and snubbers tested (Units I, IWF-5400 in accordance 2, and 3) with Technical Specification 4.18
Oconee Nuclear Station, Units 1, 2, and 3 Page 9 of 9 TABLE 1
SUMMARY
OF RELIEF REQUESTS NOTE 1:
The proposed alternative of an ID volumetric examination is acceptable only if the Licensee meets the following conditions:
(a) The remote volumetric examination includes the entire weld volume and heat affected zone instead of only the inner one-third of the weld; and (b) The ultrasonic testing instrumentation and procedure are demonstrated to be capable of detecting O.D.
surface-connected defects, in the circumferential orientation, in a laboratory test block. The defects should be cracks and not machined notches.
NOTE 2:
The proposed alternative examination should be performed in accordance with the scheduling requirements given in Table IWB-2412-1.
NOTE 3:
The proposed alternative examination is acceptable provided that, if there are full penetration repair welds associated with valve 1LP-46, a volumetric examination should be performed.
NOTE 4:
The proposed alternative examination is acceptable provided that:
(a) for partial penetration repair welds, a surface examination is performed, (b) for full penetration repair welds, a volumetric examination is performed, and (c) a visual examination is performed at operating temperature and pressure.
NOTE 5:
The proposed alternative examination is acceptable provided that, if the repair areas are full penetration welds, the volumetric examinations required by ASME Code Case N-416 are performed on both the Class 1 and Class 2 welds.
NOTE 6:
The proposed alternative examination is acceptable provided that, if the repair areas are partial penetration welds, the surface examinations required by ASME Code Case N-416 are performed.
NOTE 7:
Relief granted in accordance with 10 CFR 50.55a(a)(3)i NOTE 8:
Relief granted in accordance with 10 CFR 50.55a(a)(3)ii NOTE 9:
Relief granted in accordance with 10 CFR 50.55a(g)(6)(i)
NOTE 10: The flow tests required by IWC-5221 *and IWC-5222 are to be performed.
NOTE 11:
Confirmation of adequate flow during system operation is to be obtained in lieu of pressure testing.