ML20203H859
| ML20203H859 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/17/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20203H857 | List: |
| References | |
| NUDOCS 9902230133 | |
| Download: ML20203H859 (7) | |
Text
_ _ _ _. _ _ _. _ _. _.. _. _.
M j
. [*%g p
t UNITED STATES ~
g NUCLEAR REGULATORY COMMISSION waswoworow, o.c. sosse. coin l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE SECOND TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN bNQ ASSOCIATED REQUESTS FOR REllEF ENTERGY OPERATIONS. INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382 l
1.0 INTRODUCTION
]
Inservice inspection of the American Society of Mechanical Engineers (ASME) Code Class 1,2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel (B&PV) Code and applicable addenda as required by 10 CFR 50.55a(g),
i except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(6)(g)(i).10 CFR 50.55a(a)(3) states that altematives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty 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 pre-service 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 first ten-year interval and subsequent intervals 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) twelve months prior to the start of the 120-month interval, subject to the limitations and
- modifications listed therein. The applicable edition of Section XI of the ASME Code for the a
. Waterford-3 Steam Electre Station second ten-year inservice inspection (ISI) interval is the L 1992 Edition with portions of the 1993 Addenda. Authoilzation to use this Code Edition / Addenda of the Code was obtained in an NRC Safety Evaluation dated December 12, 1996.
By a letter dated July 1,1997, Entergy Operations, Inc. (licensee) submitted its Second
- Ten-Year interval inservice inspection Program Plan, Revision 0 and associated requests for
.1 l
EllCLOSURE 1 l
9902230133 990217 PDR ADOCK 05000382 1
8 PDR
[
N
2 relief for Waterford Steam Electric Station, Unit 3 (Waterford 3). In addition, the licensee submitted additional information and Second Ten-Year Interval inservice inspection Program Plan, Revision 1, and Associated Requests for Relief in its letter dated June 4,1998.
L 2.0 EVALUATION The staff, witn technical assistance from its contractor, the Idaho National Engineering and
?
Environmental Laboratory (INEEL), has evaluated the information provided by the licensee in support of its Second 10-Year Inservice Inspection Program Plan and Associated Requests for
' Relief, Revisions 0 and 1 for Waterford 3. Based on the results of the review, the staff. adopts -
the contractor's conclusions and recommendations presented in the enclosed Technical i
Evaluation Report.
The staff determined that there were no deviations from the regulatory requirements or commitments were identified in the licensee's Second Ten-Year Interval inservice inspection Program Plan, Revision 1 for Waterford 3.
Request for Relief No.1S12-010: ASME Code,Section XI, Table IWB-2500-1, Examination Category B-D, items B3.90 and B3.100 require that, for reactor pressure vessel (RPV) nozzle welds and inner radius sections, at least 25% but not more than 50% (credited) of the nozzles shall be examined by the end of the first inspection period and the remainder by the end of the inspection interval. Examination Category B-F, Item B5.10, Note (1) states that the reactor vessel nozzle-to-safe end weld examinations may be performed with the vessel nozzle examinations.
In accordance with 10 CFR 50.55a(a)(3)(i), the licensee proposed to use Code Case N-521 "Altemative Rules for Deferral of Inspections of Nozzle-to-Vessel Welds, Inside Radius
. Sections, and Nozzle to-Safe End Welds pf a Pressurized Water Reactor Vessel,Section XI, Division f"as an attemative to the Code requirement.
The Code requires examination of at least 25%, but not more than 50%, of RPV nozzles and associated inside radius (IR) sections and nozzle safe ends during the first inspection period.
The licensee has requested to use Code Case N-521 and defer the examination of these areas until the end of the second 10-year interval.
Code Case N-521 states that the examination of RPV nozzles, IR sections, and nozzle-to safe end welds may be deferred provided; (a) no inservice repairs or replacements by welding have
. ever been performed on any of the subject areas, (b) none of the subject areas contain identified flaws or relevant conditions that currently require successive inspections in accordance with_lWB-2420(b), and (c) the unit is not in the first interval. The licensee has confirmed that these conditions have been met. In addition, the licensee examined all the subject areas during the third period of the first 10-year interval. By examining the nozzles and associated IR sections and nozzle-to-safe end welds at the end of the previous 10-year interval, the licensee has' established a new sequence of examinations.
The staff concluded that, since the licensee will meet the conditions stated in Code Case N-521 and that the time between examinations will not exceed 10 Code Years in accordance with IWA-2430, the licensee's proposed attemative will provide an acceptable level of quality and
3 safety by providing a means to ensure structural integrity. Therefore, the licensee's proposed altemative is authorized pursuant to 10 CFR 50.55a(a)(3)(i). The use of Code Case N-521 is authorized for the second 10-year interval at Waterford 3, or until the Code Case is approved for general use by reference in Regulatory Guide 1.147. After that time, the licensee may continue to use the Code Case with the limitations, if any, listed in Regulatory Guide 1.147.
Request for Relief No. IS12-001: Use of 1992 Edition of ASME Section XI for Inservice inspection and Portions of the 1993 Addenda of ASME section XI for Pressure Testing was evaluated and authorized in NRC Safety Evaluation dated December 12,1996.
Request for Relief No.1S12-002: Use of Code Case N-546, Alternative requirements for Qualification of VT-2 Examination Personnelwas evaluated and authorized in NRC Safety Evaluation dated November 19,1997.
Request for Rt'fof No.1912-003: Use of Code Case N-509, Alternative Rules for the Selection and Examination of Class 1,2, and, Integrally Welded Attachments was evaluated and authorized in NRC Safety Evaluation dated November 19,1997.
Request for Relief No. ISl2-004: Use of Code Case N-508-1, Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing was evaluated and authorized in NRC Safety Evaluation dated July 30,1997.
Request for Rollef No. lS12-005: Use of Code Case N-524, Alternative Examination Requirements for Longitude Welds in Class 1 and 2 Piping was evaluated and authorized for Class 1 components only in NRC Safety Evaluation dated September 17,1997.
Request for Relief No.1S12-005: Use of Code Case N-524, Alternative Examination Requirements for Longitude Welds in Class 1 and 2 Piping was evaluated and authorized for Class 2 components only in NRC Safety Evaluation dated November 19,1997.
Request for Relief No. IS12-006: Use of Code Case N-416-1, Alternative Pressure Test requirement for Welded Repairs or Installation of Replacement items by Welding, Class 1,2, and 3 was evaluated and authorized in NRC Safety Evaluation dated September 4,1997.
Request for Rollef No. IS12-007: Use of Code Case N-532, Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report.
Preparation and Submission as Required by IWA-4000 and IWA-6000 was evaluated and authorized in NRC Safety Evaluation dated September 4,1997.
Request for Relief No. ISl2-008: System Pressure Test Corrective Actions was evaluated and authorized in NRC Safety Evaluation dated April 7,1998.
Request for Rollef No.1S12-009: System Pressure Tests for Insulated Components was evaluated and authorized in NRC Safety Evaluation dated December 1,1998.
-__ _ _ _ _ q 4
1
3.0 CONCLUSION
S i
i The staff conclude that there are no deviations from the regulatory requirements or commitments that were identified in the licensee's Second Ten-Year Interval inservice Inspection Program Plan, Revision 1 for Waterford 3.
The staff conclude that for the licensee's altamative contained in Request for Relief No.
l lSl2-010 provides an acceptable level of quality and safety and is authorized pursuant to j
l Request for Relief No. ISl2-001 was previously evaluated and authorized in NRC Safety i
Evaluation dated December 12,1996. The staff concludes that the licensee's proposed alternative remains authorized as evaluated in NRC Safety Evaluation dated December 12, i
1996 l
t Requests for Relief Nos.1S12-002,1S12-003, and 1S12-005 were previously evaluated and
'j authorized in NRC Safety Evaluation dated November 19,1997. The staff concludes that the licensee's proposed attemative remains authorized as evaluated in NRC Safety Evaluation dated November 19,1997.
s Request for Relief No. ISl2-004 was previously evaluated and authorized in NRC Safety Evaluation dated July 30,1997. The staff concludes that the licensee's proposed alternative remains authorized as evaluated in NRC Safety Evaluation dated July 30,1997.
Requests for Relief Nos. ISl2-006, and ISl2-007 were previously evaluated and authorized in NRC Safety Evaluation dated September 4,1997. The staff concludes that the licensee's
(
proposed alternatives remain authorized as evaluated in NRC Safety Evaluation dated l
September 4,1997.
Request for Relief No.1S12-008 was previously evaluated and authorized in NRC Safety Evaluation dated April 7,1998. The staff concludes that the licensee's proposed alternative remains authorized as evaluated in NRC Safety Evaluation dated April 7,1998.
Request for Relief No.1S12-009 was previously evaluated and authorized in NRC Safety Evaluation dated December 1,1998. The staff concludes that the licensee's proposed
. alternatives remain authorized as evaluated in NRC Safety Evaluation dated December 1, 1998.
A table summarizing the status of the Relief Requests is attached.
Attachment:
As stated Principal Contributor: T. McLellan Date:
February 17, 1999
~
(
5 i
Waterford Steam Electric Station, Unit 3 Page 1 of 3 Second 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS -
y Re5ef l
Request System or Exam hem Licensee n ;:::f i
Number Component Category No.
Volume er Aree to be Examined Required Method Altemative Relief Request Status i
1S12-001 Class 1, 2, and All All All Required All Code Use of 1992 Ed: tion of Authorized in NRC SE 3 components Requirements ASME Section XI for dated December 12, i
Inservice Inspection and 1996 portions of the 1993 Addenda of ASME Section XI for pressure tests 1S12-002 Qualification of IWA-23OO Qualification of VT-2 Personnel Visual, VT-2 Use of Code Case N-546 Authorized in NRC SE VT-2 Personnel dated November 19,
[
1997 l
1 1S12-003 Integral B-H,B-K, Altemative rules of selection of Volumetric or Use of Code Case N-509 Authorized in NRC SE Attachments C-C, integrally welded attachments surface dated November 19, D-A, D-C examination 1997 1S12-004 Snubbers and IWA-4000 Rotation of Serviced Snubbers and Use of Code Case N-508-1 Authorized in NRC SE Pressure Relief Pressure Relief Valves for the Purpose dated July 30,1997 Valves of Testing ISl2-OO5 Class 1 and 2 B-J Longitudinal Welds Volumetric and/or Use of Code Case N-524 Authorized in NRC SE piping C-F-1 Surface dated September 17, C-F-2 1997 7
1S12-006 Repairs and NA NA Pressure Tests Following Repairs and NA Use of Code Case N-416-1 Authorized in NRC SE Replacements Replacements dated September 4,
[
1997 T
3 6
Waterford Steen Electric Station, Unit 3 -
Page 2 of 3-Second 10-Yeer ISI interval TABLE 1
SUMMARY
OF RELIEF REOUESTS ReBet
~
t Request System er Exam -
Item Licensee Propooed
[
Number Component Category No.
Volume or Area to be Examined Required Method Altemative
' Resef Roguest Status t
ISi2-007 Repair and IWA-4000 Altemative requirements to repair and Use of Code Case N-532 Authorized in NRC SE i
Replacement IWA-6000 replacements documentation dated September 4 Documentation requirements and inservice summary -.
1997 i
report preparation and submession
-[
IS12-008 Class 1,2, and IWA-5250 NA Leaking Bolted Connections if leakage occurs Perform an evaluation of -
Authorized in NRC SE 3 piping at a bolted the bolted connection to dated April 7,1998 -
l connection, one -
determene the
-i bolt closest to the susceptibility of the botting leak shall be to corrosion and the removed and VT-3 potential for failure. If the j
exammed evaluation indicates the need for further evaluation,
[
the actions specified in i
IWA-5250(aH2) shall be.
I performed
[
r IS12-009 Class 1 and 2 IWA-Pressure retaining bolted connections Visual VT-2 Perform a VT-2 visual Authorized in NRC SE
{
borated system 5242(a) examination wie removing dated December 1 insulation. If there is 1998 h
evidence of boric acid, remove insulation and re-
[
examine Insulation at bolted I
connections shall be f
removed during each
[
refueling outage and perform a VT-2 visual j
examination.
)
t f
i
-. ~ ~., _ _ -. -
7
! Waterford Steam Electric Station, Unit 3 Page 3 of 3 Second 10-Year ISI Interval TABLE 1
SUMMARY
OF RELIEF REQUESTS Relief Requoet System or Exaen item Licensee N:;: _ : f Number Component Category No.
Volume or Area to be Examined Required Method Altemative Retof Request Status 1512-0 1 0 Reactor Vessel B-D B3.90 Nozzle-to-Reactor Vessel Weld Volumetric -
Perform the examinations Authorized Nozzles 83.10 Nozzle inside Radius Sections concurrent with the reactor B-F B5.10 Nozzle-to-Safe End Welds Volumetric and vessel ten-year Surface examinations at or near the end of the inspection intervalin accordance with N-521 i
i
{
l 9
i I
=
.