ML19354D703
| ML19354D703 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/26/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19354D702 | List: |
| References | |
| NUDOCS 8912290129 | |
| Download: ML19354D703 (10) | |
Text
F..
1 ENCLOSURE
(- 3 SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE FIRST TEN YEAR INTERVAL INSERVICE INSPECTION RELIEF REQUESTS NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NUMBER:
50-333 i
1,0- INTRODUCTION 4
The James A. FitzPatrick Nuclear Power Plant First 10 Year Interval Inservice Inspection (ISI) Prograt,. Plan was previously evaluated in the Nuclear Regulatory Commission's (NRC) Safety Evaluation Report (SER) dated January 31, 1984 and was determined to be acceptable for implementation during the first inspection interval.
This SER also granted, conditionally granted, or denied requests for relief.
The first 10-year inspection interval ended July 28, 1985.
On August 6, 1987, the Licensee, New York Power Authority, submitted additional requests for relief from the 1974 Edition through Summer 1975 Addenda of Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code requirements which the Licensee has also determined to be impractical for the first 10-year inspection interval.
As a result of the review of the August 6, 1987 submittal, a request for additional information (RAI) was prepared describing the information and/or clarifications required from the Licensee in order to complete the review.
The Licensee provided the additional information in a letter dated September 20. 1988.
Pursuant to 10 CFR 50.55a(g)(5)(iii), 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 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 not endanger life or property or the common defense and security, and bb$$$o$
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are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.
The staff, with technical assistance from its Contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the additional requests for relief from certain ASME Code requirements detemined to be impractical for James A.
FitzPatrick Nuclear Power Plant for the first inspection interval.
2.0 EVALVATION AND CONCLUSION 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 the attached.INEL Technical Evaluation Report (EGG-ESM-79233 We concur with, and adopt, the findings and recommendations contained in the subject report. Table 1 presents a sunvary of the reliefs requested and the status of the requests as detemined by the staff.
It should be noted that relief that is requested solely because an inspection was missed is normally not considered. However, four of the requests for relief (la, 9.11, and 12) have been granted because either essentially 100% of the minimum Code requirement has been met or the Licensee committed to complete the missed examination during the first part of the second inspection interval. New York Power. Authority should be more diligent in documenting examinations and examination resutis, thereby eliminating the need for these types of relief requests.
For the relief granted, it has been determined that (a) pursuant to 10 CFR 50.55a(a)(3)(ii), compliance with certain code sections will result in undue hardship without a compensating increase in the level of safety and (b) pursuant to 10 CFR 50.55a(g)(6)(1), the requirements of the code are impractical and, based on the alternative requirements imposed, relief is authorized by law, will not endanger life or property or the coninon defense and security, and is otherwise in the public interest. Such relief has been granted giving due consideration to the burden on the licensee that could result if the requirements were imposed on the facility.
DATED:
-o James A. FitzFatrick Nuclear Power Plant Page 1 of 8 1ABLE I
SUMMARY
Of REIIff RIOUESTS Relief Licensee Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component Cat.
No.
to be Examined Method Alternative Status la Reactor B-B Bl.2 Top Closure Head Volumetric None (0.4%
Granted Pressure Meridional Welds:
volume missed Vessel VV-TH-IA VV-TH-lE due to VV-TH-1B VV-1H-lf administrative VV-TH-lC VV-TH-lG error)
VV-TH-ID VV-TH-lH lb Reactor B-B Bl.2 Bottom Closure Head Volumetric Mone Granted Pressure Meridional Welds:
(volumetric Vessel VV-BH-2A VV-BH-20 examination to-VV-BH-28 VV-BH-2E maximum extent VV-BH-2C VV-BH-2F practical) t 2a Reactor B-D Bl.4 Nozzle-to-Vessel Welds Volumetric None Granted Pressure and Nozzle Inside Radius (volumetric Vessel Sections:
examination to N-2A N-2E N-2H maximum extent N-2J N-3C N-8B practical) 2b Reactor B-D Bl.4 Nozzle-to-Vessel Welds Volumetric None Granted Pressure and Nozzle Inside Radius (volumetric Vessel Sections:
examination to N-1A N-2D N-4A maximum extent N - Ill N-2f N-4C practical)
N-2il N-2G N-5B N-2C N-2K
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James A. FitzPatrick Nuclear Power Plant Page 2 of 8.
lABLE l'
SUMMARY
Of RELIEF REQUESTS Licensee Relief Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component Cat.
No.
to be Examined Method Alternative Status 6
Reactor B-G-2 B1.11 Pressure Retaining Visual None (visual Granted P essure Bolting:
examination of Vessel 137 Control Rod Drives bolting when Bolting and 43 Incore made accessible Instrumentation during Penetrations maintenance or replacement) 3 Class 1 B-F Bl.6 Jet Pump Instrumentation Volumetric None Granted
- Dissimilar Nozzle Safe-end Welds:
and Metal Welds NBA-SE Surface N88-SE Class 1 B-J B4.6 "A" Jet Pump Assembly Volumetric None Granted
- Branch Welds:
Eonnection N8A-SE-1 Welds N8A-SE-2
subject N88-SE-1 welds N88-SE-2 during 2nd N88-SE-3 10-year 4-118 inspection interval mi
James A. FitzPatrick Nuclear Power Plant
'i Page 3 of 8 TABLE I St::1 MARY Of RELIEF REQUESTS Relief Licensee Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component Cat.
No.
to be Examined-Method Alternative Status 4
Class 1 B-F B4.1 RHR System Bimetallic Volumetric None Granted Piping Welds:
and (100% surface Dissimilar 24-10-130 24-10-142 Surface examination and Metal Welds 24-10-131 24-10-143 Volumetric 24-10-132 24-10-144 examination to maximum extent practical) 5 Class 1 B-G-2 B4.12 RHR System Head Spray Visual None Denied Flange Line Flanges:
Bolting A, B, C, and D W
I' i
James'A. FitzPatrick Nuclear Power Plant Page 4 of 8 IABLE I SUMMARV Of RELIEF-REQUESTS Relief Licensee Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component Cat.
No.
to be Examined Method Alternative Status 7
Class 1 B-G-2 B6.9 RR System Valves:
Visual None Denied Valve 02-MOV-43A, -438, -53A, Bolting
-538
-54A, -548 RHR System Valves:
RHR-29, -81A, -818,
-88, 10-A0V-25A, -258, -32,
-33 RWCU System Valves:
12-MOV-15, -18, -68, RWC-46, -62, -68 RCIC System Valves:
13-MOV-15, -16, -21,
-22 CS System Valves:
14-MOV-12A, -128 HPCI System Valves:
23-MOV-15, -16, -18,
-19 MS System Valves:
29-RV-7]A, 29-A0V-80A FW System Valves:
IWS-29A, -298, 34-NRV-Illa
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h James A. FitzPatrick Nuclear Power Plant-Page 5 of 8 TABLE I
SUMMARY
OF RELIEF REQUESTS Relief Licensee Relief Request System or Exam.
Item Volume or Area Required Proposed Request.
Number Component Cat.
No to be Examined' Method Alternative Status _
10 Class 1 8-M-2 B6.7 RR System Valves:
Visual None Granted Valve 02-MOV-43A, -43B, -53A, Internal
-538, -54A, -54B Surfaces
- Rt!R System. Valves:
RHR-29,
-81A, -88, 10-A0V-25A, -258, -32,
-33 RWCU System Valves:
12-MOV-15, -18, -68, RWC-46, -62, -63 RCIC System Valves:
13-MOV-15, -16. -21,
-22 CS System Valves:
H-MOV-12A, -128, CSP-14A, -14B HPCI System Valves:
23-MOV-15
-16, -18,
-19 Mi System Valves:
23-RV-71A, B, C, D, E, F, G, K, L, J, 29-A0V-80A, -86A FW System Valves:
34-NHV-Illa, IWS-28A, -288, -29A,
-29H
a.
James A. F'tzPatrick Nuclear Power Plant i
Page 6 of 8 TABLE I
SUMMARY
Of REL EF REQUESTS Licensee Relief' Relief Request System or Exam.
Item Volume or Area.
Required Proposed Request Number Component Cat.
No.
to be Examined' Method Alternative Status 8
Class 1 B-K-1 84.9 RR System Supports:
Volumetric None Granted Integrally 85.4 22-02-2-22A, -228, -318, Welded 86.4
-31D, -86A, -87A, Supports
-878, -89A, -898,
-89D, -Il0F,-143,
-145, -150, -151,
-156, -158, -1468 RHR System Supports:
24-10-132A, -1328, -989,
-992, -993 HPCI System Supports:
10-23-668A, 14-23-428A MS System Supports:
24-29-519A, -522A, -542C,
-543C, -5430, -550A,
-557A, -5698, -574C,
-593,
-6070, -626A,
-5740, 37-29-573C FW System Supports:
12-34-401A, -944, 18-34-937A
9 James A. FitzPatrick Nuclear Power Plant Page 7 of 8 IABLE I
SUMMARY
OF REllEF REQUESTS Licensee Relief Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component Cat.
No.
to be Examined Method Alternative Status 9
Class 1 8-K-2 84.10 RR System Supports:
Visual None Granted
- Component B5.5 02-2-18-S-15 (examinations Supports 86.5 02-2-28-S-4 missed due to 02-2-98-AN-10 administrative
- Based on error)
Licensee RHR System Supports:
commitment 10-20-AN-205 to examine 10-43-AS-236 the subject 10-14A-NS-2409 welds 10-43-AN-229 during the 10-43-AN-230 ist half of the 2nd RWCU System Support:
10-year 12-14-NS-12 inspection interval RCIC System Support:
13-4A-NS-IA MS System Supports:
29-IC-AN-238 29-IC-AN-28 29-ID-AN-40A 12 Class 2 C-G C2.1 To meet Licensee's Volumetric None Granted Piping C2.2 commitment to the NRC, (examinations Welds C2.3 two additional welds in missed due to the Containment Air
' administrative Dilution System required error) examination'during the 1st 10-year inspection interval.
B.
James A. FitzPatrick Nuclear Power Plant Page 8 of 8 1ABLE 1
SUMMARY
Of RELIEF REQUESTS Relief Licensee Relief Request System or Exam.
Item Volume or Area Required Proposed Request Number Component
_ Cat.
No.
to be Examined Method
__ Alternative
. Status 11 Class 2 C-E-1 C2.5 To meet the Licensee's Surface None Granted
- Integrally C3.3 commitment to the NRC, 22 (examinations Welded C4.3 additional Class 2 missed due to
- Based on Supports integrally welded administrative Licensee supports required error) commitment examination during the to examine 1st 10-year inspection the subject
- interval, welds during the 1st half of LSe 2nd 10-year i
inspection interval i
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