ML17320A480
| ML17320A480 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/15/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17320A479 | List: |
| References | |
| NUDOCS 8304270041 | |
| Download: ML17320A480 (13) | |
Text
SAFETY EVALUATION BY THE OFFICE OF NUCL A R ACTOR R GULATION R LA 0
TO RE UESTS FOR R LI F FROM INS RVICE INSPEC ION R
UIREMENTS Indiana and Michi an Electric Co.
Donald C.
Cook Units 1 and 2
DOCKET NOS. 50-315 AND 316 INTRODUCTION Technical Specification 4.4.10 for the Donald C.
Cook Nuclear Power Plant Units 1 and 2 states that inservice examination of ASME Code Class 1, 2, and 3
components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission.
Certain requirements of later editions and addenda of Section XI are imprac-tical to perform on older plants because of the plants'esign, component
- geometry, and materials of construction.
- Thus, 10 CFR 50.55a(g)(6)(i)-
authorizes the Commission to grant relief from those requirements upon making the necessary findings.
By letters dated November 18,
- 1977, September 22, 1978, August 25,
- 1978, September ll, 1979, July 2, 1982, September 2, 1982, and September 23, 1982, Indiana and Michigan Electric Company submitted its inservice inspection
- program, revisions, or additional information related to requests for relief from certain Code requirements determined to be impractical to perform on the Donald C.
Cook Nuclear Power Plant Units 1 and 2 during the inspection interval.
The program is based on the 1974 Edition including Summer 1975 Addenda or Section XI of the ASME Code, and covers the following periods:
o Unit 1 - Second and Third 40-month periods of the first interval (December 23, 1978 to August 23, 1985) o Unit 2 - The entire first ten-year interval from July 1, 1978 to July 1, 1988.
EVALUATION Requests for relief from the requirements of Section XI which have been determined to be impractical to perform have been reviewed by the Staff's contractor, Science Applications, Inc.
The contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the Technical Evaluation Report (TER) attached (ATTACHMENT 1).
The staff has reviewed the TER and agrees with the evaluations and recommendations.
A summary of the determinations made by the staff is presented in the following tables:
8304270041 830415 PDR ADOCK 05000315 8
I I+
TABLE 1 CLASS 1 COMPONENTS LICENSEE PROPOSED IWB"2600 IWB-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
EXAM.CAT. COMPONENT EXAMINED METHOD EXAM STATUS Bl. 2 B-B Reactor Vessel Circumfer-ential seal welds in closure head:
1-C-02 and 2-CMC-02 Volumet-ricc None Granted Provided:
o The Accessible portion of each dollar head weld is examined.
o The examination of accessible Category B-B welds is increased to achieve a sample whose total length includes the weld for which relief was requested.
Bl. 3 (Unit 2 only)
B-C Reactor Vessel Cl osure Head Flange Weld Volumet-Examine ric 100K 96K of of weld weld Granted B2. 2 (Unit 2 only)
B-D Pres-sur izer Nozzle-to-Volumet-Vessel Weld ric on surge line Volumetric examination from vessel side only Granted provided that a full Vee volumetric examination is con-ducted from the acces-sible side and supplemented with surface exam.
B2. 8 (Unit 2 only)
B4. 5 (Unit 1 only)
B-H B-J Pres-surizer Reactor Coolant System and Chemical and Volume Control System Integrally Welded Vessel Support.
2-PRZ-20 Pipe Wel ds No.
015 and 23F Volumet-ric Volumet-ric 100K of weld UT Along the acces-sible length Examine 82K of of weld No.
015 and 83K of weld No.
23F Granted Granted
TABLE 1 Continued CLASS 1 COMPONENTS IWB-2600 IWB-2500 SYSTEM OR ITEM NO.
EXAM.CAT. COMPONENT AREA TO BE REQUIRED EXAMINED METHOD LICENSEE PROPOSED ALTERNATIVE RELIEF RE(UEST EXAM STATUS B4. 6 B-J (Unit 2 only)
Piping Branch Pipe Connection Weld No.
OBN Volumet-ric Volumetric to extent practical supple-mented by surface Granted B4. 9 B-K-1 (Unit 1)
B4. 9 B-K-1 (Unit 2)
Reactor Coolant and Safety Injection Reactor
- Coolant, Safety Injection, and Chemical and Volume Control Systems Integrally-Volumet-Welded ric Piping Supports:
24-F"HL-1 24F" HL-2 24F" HL-3 24F-HL"4 03S"RL"4 27S"PR"1 135" PS 29S-RL-1 29S"Rt"2 29S-RL=3 15F"PS-2 51S 27S"HL-1 23S-HL-3 23S"HL-4 Integrally-Volumet-Welded ric Piping Supports:
PR1-PL-2 (LTP REF No.
047500)
PR1-PL'-2 (LTP REF No.
047500)
PR1" PL-2 (LTP REF No.
047600)
PR1-PL-1 (LTP REF No.
054800)
(a)AA (a)
(a)
(a)
(a)
(a)
(c)
(a)
(a)
(a)
(e)
(c)
(e)
(e)
(e)
(a)
(a)
(a)
(a)
Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Granted Gr anted Granted Granted Granted
IWB"2600 IWB"2500 SYSTEM OR ITEM NO.
EXAM.CAT. COMPONENT TABLE 1 (Continued)
CLASS 1 COMPONENTS LICENSEE PROPOSED AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST EXAMINED METHOD EXAM STATUS B4. 9 (Unit 2)
(Cont.)
PR1" PL-2 (LTP REF No. 054900)
PR1" PL-3 (LTP REF No.
055000)
PR" 1"PL"1 (LTP REF No.
088000)
P R PL"2 (LTP REF No.
088050)
PR1-PL-1 (LTP REF No.
130000)
PR1-PL-1 (LTP REF No.
134300)
(a)
(a)
(a)
(a)
(a)
(a)
Granted Granted Granted Granted Granted Granted B4. 9 B-K-1 Reactor Coolant Pumps Integrally-Volumet-Surface Welded ric Support Lug Welds Granted B5. 6 B-L-1 Reactor Coolant Pumps Pump Casing Welds Volumet-
- ric, Weld and Base Metal one wall thickness beyond edge of weld Volumetri c, Granted Weld and Base Metal inch on either side of weld
"~ (a)
Volumetric supplemented by surface (c)
Surface only (e)
Examine at least 75K of weld
IWC-2600 IWC-2520 SYSTEM OR ITEM NO.
EXAM.CAT. COMPONENT TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST EXAMINED METHOD EXAM STATUS C2. 1 C2. 1 C-G C"G Main Steam and Feedwater Main Steam Piping Welds in Contain-ment Penetra-tions Piping Welds covered by whip restraints Volumet-ric Volumet-ric None None Granted provided that the first accessible weld outside the pene-tration is examined.
Granted provided that an adjacent weld in one main system line is examined.
C2. 3 C-G Main Steam Safety Valve Header and Feedwater Branch Connec-tions Volumet-ric Surface Granted C2. 1 C2. 1 C2. 1 C-G C-G C-G Contain-ment Spray System Emergency Core Cooling System CVCS-Reactor Letdown and Charging All Piping Welds Piping Welds Welds in Following:
(1) Volume Control Tank to Charging Pump (Unit 1)
Volumet-ric Volumet-rlc Volumet-ric Visual Visual Visual Not Granted Not Granted Not Granted TABLE 2 (Continued CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2600 IWC-2520 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO.
'EXAM.CAT. COMPONENT EXAMINED METHOD EXAM STATUS C2. 1 (Cont. )
(2) Re-fueling water storage tank to Centri-fugal Charging Pump (3) Supply Header to Centri-fugal Charging Pump "E" (4) Supply Header to Centri-fugal Charging Pump "M"
TABLE 3 CLASS 3 COMPONENTS
)No Relief Requests]
TABLE 4 PRESSURE TEST SYSTEM OR COMPONENT IWA-5000 IWB-5000, IWC-5000, AND IWD"5000 TEST PRESSURE REQUIREMENT LICENSEE PROPOSED ALTERNATIVE TEST PRESSURE RELIEF REQUEST STATUS
[No Relief Requests]
Ifa
TABLE 5 ULTRASONIC EXAMINATION TECHNI UE SYSTEM OR COMPONENT REQUIREMENT LICENSEE PROPOSED ALTERNATIVE TEST PRESSURE RELIEF REQUEST STATUS
[No Relief Requests]
TABLE 6 GENERAL RELIEF RE UESTS ALL CLASSES/COMPONENTS SYSTEM/COMPONENT REQUIREMENT LICENSEE ALTERNATIVE RELIEF REQUEST STATUS
[No Re1ief Requests]
0 Based on the review summarized, the staff concludes that relief granted from the examination requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity, that granting relief where the Code requirements are impractical is authorized by law and wil'1 not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on the facility.
Environmental Considerations We have determined that granting relief from specific ASNE Section XI Code requirements does not authorize a change in effluent types or total amounts nor en increase in power level and will not result in any significant environ-mental impact.
Having made this determination, we have further concluded that this is an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an environmental impact state-ment or negative declaration and environmental impact appraisal need not be prepare'd in connection with the grant of this relief.
Conclusion Me have concluded, based on the considerations discussed above, that:
(1) because the actions do not involve a significant increase in the probability or consequences of an accident previously evaluated, do not create the possibility of an accident of a type different from any evaluated previously, and do not involve a significant reduction in a margin of safety, the actions do not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of the actions will not be inimical to the common defense and security or to the health and safety of the public.
4PR
) 5 l983 Principal Contributor:
G. Johnson