ML102980529
| ML102980529 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 04/27/2010 |
| From: | O'Hara T NRC Region 1 |
| To: | Conte R NRC Region 1 |
| References | |
| FOIA/PA-2010-0334 | |
| Download: ML102980529 (3) | |
Text
OHara, Timothy I
From:
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OHara, Timothy V %
Tuesday, April 27, 2010 1:09 PM Conte, Richard FW: Scan from Salem/Hope Creek HP5035 Scan File.pdf
- Rich, Attached are the applicable Salem Unit 1 Technical Specifications for structural integrity. Other surveillances cover testing of pumps and valves.
Tim OHara Original Message -----
From: RlScan [1]
Sent: Tuesday, April 27, 2010 12:15 PM To: OHara, Timothy
Subject:
Scan from Salem/Hope Creek HP5035 Please open the attached document. This document was digitally sent to you using an HP Digital Sending.
device.
C
REACTOR COOLANT SYSTEM 3.4.10 STRUCTURAL INTEGRITY ASME. CODE CLASS 1, 2 and 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.1.
APPLICABILITY:
ALL MODES ACTION:
- a.
With the structural integrity of any ASME Code Class I omponent(s.)
not. conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) pribr to increasing the Reactor Coolant system temperature more than 50°F above the minimum temperature required by NDT considerati6ns.,
- b.
With the-structural integrity of any ASME Code Class :2 component(s) not c6nforming to the above requirements, restore the structural integrity of the affected component(s)-to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 2000 F.
- c.
With the structural integrity of any ASME not conforming to the above requirements, integrity of the affected component(s) to the affected component(s) from service.
Code Class 3 componentý(s) restore the structural within its limit or isolate SURVEILLANCE REQUIREMENTS 41.4.10.1.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be demonstrated:
- a.
Per the requirements of Specification 4.0.5, and
- b.
Per the requirements of the augmented inservice inspection program specified in Specification 4.4.10.1.2.
11SALEM -'UNIT 1
3/A4 4-32 AAmendment No.
276
4 REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)
In addition to the requirements of Specification 4.0.5, each Reactor Coolant Pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1, August 197:5.
In l'ieu of Position CA4.b(1) and C.4..b(2),
a qualified in-place UT examination over the volume from the inner bore of, the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
4.4.10.1.2 Augmented Inservice Inspection Program for Steam.Generator Channel Heads -
The steam generator channel heads shall be ultrasonically inspected during each of the first three refueling outages usihg the same ultrasonic inspection procedures and equipment used to generate the baseline data., These inservice ultrasonic inspections, shall verify that
- the
- cracks observed in the stainless steel*cladding pribo-to operation have not propagated into the base material, The stainlesf steel clad surfaces of the steam generator channel heads shall also be visual1y inspected during the above outages.
This may be accomplished by direct visual examination or by remote means such as television camera.
if the visual examination, either direct or remote,, reveals detec't~able cladding indications, a record shall be made by means of a video tape recording or photographs for comparison purpobseS.
- SALEM
- UNIT I 3/4 4 -3:3 Amendment No.
265