ML20010A297
| ML20010A297 | |
| Person / Time | |
|---|---|
| Site: | San Onofre |
| Issue date: | 08/13/1980 |
| From: | Kaminski D, Michelsen M, Sheffield W ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY |
| To: | |
| Shared Package | |
| ML13323A163 | List: |
| References | |
| 1370-RCE-413, NUDOCS 8108110289 | |
| Download: ML20010A297 (6) | |
Text
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PRECRITICAL VIBRATION MONITORING PROGRAM PROJECT PROCEDURE RECEIVED FOR p
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JUL 101981 VISUAL IHSPECTION H.B. RAY OF
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REACTOR VESSEL INTERNALS FOR SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 and 3 SPECIFICATION HO.1370-RCE-413 Prepared By:
Date S-/l' W M. A. Michelsen, Project Applications Engineer Date 9 /3/go Approved By: M.b-[=
D. J. Kamins 1, Cognizant Engineer Approved By:
dA7 Date 5
W 7.
ff d Supervisor, Core Support Structures bM Au
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Date Approved By:
m f. 'T iru lich, Manager, Reactor Comp. Engineering 844 7 Dcte h-/I-h l
Approved By:.
~S. Bruggtty Quality control T2 l
This document is the property of Combustion Engineering, Inc.
(C-E), Windsor, Connecticut and is to be used only for the purpose of the agreement with C-E pursuant to which it is furnished.
Issue Date:
August 13_ 1980
. Revision 00 at.cd6
. N J..uu G
EDg/GO bgegg(({gggg!3 Page 1 of 6
This procedure together with the Standard Procedure 00000-RCE-413. Revision 00, constitute the Precritical Vibration Monitoring Program (PVMP) procedure for visual inspection of reactor vessel internals for the Southern California Edison Company's San Onofre Huclear Generating Station -- Unit Number 2 and 3, located four miles south of San Clemente California.
The requirements of the Standard Procedure apply, except as modified below:
Specification No, Modification by Specification 00000-RCE-413 No. 1370-RCE-413 page iii Replace page iii of 00000-RCE-413 with page 3 of 1 through page 4
of 6 of 13E-RCE-413, attached, page 17 Replace page 17 of 00000-RCE-413 with page 5 of 6 of 1370-RCE-413, attached The " Visual Acuity Test" shall be a Section 7.0, Page 33 Jaeger Test, a Snellen Test and an Ishihara Color Examination.
Page 33A and Pages 33A and 33B shall be available at the time of the inspection to Page 33B document the results of the inspector (s) visual acuity test and the inspector (s) experience and education; they shall be attached to the final inspection report.
Page 35 Replace page 35 of 00000-RCE-413 with page 6 of 6 of 1370-RCE-413, attached.
Throughc:it The inspector (s) shall s h and date each paSe of data.
HRC Regulatory Guide 1.20, gevision 1 requires that the reactor internals components be subjected to at least 10 cycles of vibration for the purposes of the PVMP.
Based on a calculated minimum natural frequency of 4.9 hertz (for the Core Support Barrel),
24 days of primary flow will be required during the pre-core hot functional tests for SONGS-2 and 3.
To support.the verification of accomplishment of the minimum cycles of vibration, the Owner (SCE) will record the individual and collective Reactor Coolant Pump running times during the pre-core hot functional testing, for both above 560'F and below 360'F operation, and will submit those times to C-E after coupletion of the testing.
e Specification No.1370-RCE-413 Page 2 of 6 Revision 00
PVMP PROCEDURE FOR VISUAL INSPECTION OF REACTOR VESSEL INTERNALS FOR SAN ON0FFE UNITS 2 and 3 The Precritical Vibration Monitoring Program (PVMP) for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, will be performed in accordance with NRC Regulatory Guide 1.20, Revision 1.
SOHGS 2 and 3 have been designated Non-Prototype, Category 1, reactors for the purpose of the PVMP (The Maine Yankee and Fort Calhoun reactors am jointly designated as the valid prototype ; see SONGS 2 and 3 FSAR Section 3.9.2.4) and as such require a visual inspection of reactor internals. This procedure for visual inspection of reactor vessel internals is in accordance with NRC Regulatory Guide 1.20, Revision 1.
Visual examination of the internals will be performed in two stages, a baseline re-view and a post-hot functional (pre-core) test review. The components and areas to be inspected are defined in this procedure ; the inspections will be performed within the guidelines specified below:
(a) The visual examination shall be conducted to detennine the general mechanical and structural conditions of components and their supports, such as the presence of loose parts, debris, or abnonnal corrosion products, wear, erosion, corrosion and the loss of integrity at bolted or supporting elements.
(b) The visual examination will' require, as applicable to detennine structural integ-rity, the measurement of the clearances and the detection of physical displace-ment between supporting elements.
l (c) For component supports and component interiors, the visual examination may be l
performed remotely with or without optical aids to verify the structural integrity l
of the component.
(d) Direct visual examination may be conducted when accass is sufficient to place the eye within 24 in. (610 m) of the surface to be examined and at an angle not less than 30 deg. to the surface. M'.rrors may be used to improve the angle of vision.
Lighting, natural or artificial, shall be sufficient to resolve a 1/32 in.. (0.8 m) black line on an 18% neutral gray card.
Page iii of Specification No. 00000-RCE-413 As Hodified By:
Revision 00 Specification No.1370-RCE-413 Page 3 of 6 ll.
The inspector (s) shall be qualified in accordance with Section 7.0, " Inspector Qualification Requirements", of this procedure.
In addition, at least one in-spector shall be qualified and certified as a Level 2 visual inspector in accor-dance with the intent of Regulatory Guide 1.58, Revision 0; C-E Procedure No.
9976-HLE-040, Revision 1, " Standard Operating Procedure for Certifying Visual Examination Personnel for Preservice/ Inservice Examinations", shall be used to certify the qualification of the Level 2 visual inspector. A copy of the Level 2 inspector's certification records shall be available at the time of the PVMP j
inspections, and shall be attached to the final inspection report.
Verification of perfortnance of the inspections to this procedure shall be assured by the signature of a qualified auditor following each inspection series (see Enclosure (1),"QA Auditor's Check Off List"); certification of the auditor's qual-ifications shall be in accordance with C-E's Group Quality Assurance Manual Rev-ision A.
Documentation of that certification (page 17a/35a of this procedure) shall be available at the time of the audit, and shall be attached to the final inspection report.
The inspection report shall include a copy of this procedurt with completed data sheets and a summary of the significant findings of the engineering evaluations.
If the inspection of the reactor internals reveals 1) defects, evidence of un-acceptable motion, excessive or undue wear, or 2) the results from the analysis the valid prototype (s) ), or inspection (of the valid prototype (s) performed (previously performed for SOK.S 2 and 3), measurement (previously and SONGS 2 and 3) programs are inconsistent, the report shall also include an evaluation and description of the modifications or actions planned in order to justify the st? uctural adequacy of the reactor internals. Specifically, the inspection re-port will contain the following items as a minimum:
Identification of the reactor plant; s.
b.
Date of the inspection; A copy of the procedure used; c.
d.
Names and qualifications of personnel performing the inspection; e.
Signature of the auditor; f.
A qualification reccrd of the auditor; Data sheets with component descriptions and photographs per the procedure; g.
Photographs of the inspected components,taken during each inspection; h.
A detailed comparison of the component's wear characteristics, as observed i.
during the baseline and post-hot functional test inspections;
- j. A summary of the significant findings of the engineering evaluations.
Page 111 of Specification No. 00000-RCE-413 As Modified By:
Specification No.1370-RCE-413 Page 4 of 6 Revision 00
EHCLOSURE(1)
Q.A. AUDITOR'S C"ECK OFF LIST r
Reactor Vessel Internals Pre-Critical Vibration Visual Monitoring Program Ref.
(a):
Project Procedure for Visual Inspection of Reactor Vessel Internals for SONGS 2 and 3. C-E Specification No.1370-RCE-413 (b):
CE-GQC Surveillance Trip Report dated The following items are to be considered during each evaluation of the subject program. This sheet shall be completed, signed, and attached to the data being attained by the inspector. Details of verification of (1) through (7) below shall be recorded in Reference (b).
i 1.
Has the inspector obtained certification of his visual ability in accordance with Reference (a)?
2.
Has the inspector been certified to be technically qualified in accordance with Reference (a)?
t 1
3.
Is the inspector making adequate notations of the internals condition?
i 4.
Is the inspector adequately completing the data forin in accordance with Reference (a)?
5.
Is the inspector utilizing the current revision of Reference-(a)?
6.
Is the inspector carrying out the examination in accordance with the requirements of lighting, distance, and angle specified in Reference (a)?
l 7.
Is the inspector verifying that he has adequate resolution in ac-I cordance with the requirements of Reference (a)?
l Signature /Date i
Page 17 of Specification No. 00000-RCE-413 As Modified By:
Specification No.1370-RCE-413 Page 5 of G Revision 00
EHCLCSURE (1)
Q.A. AUDITOR'S CHECK OFF LIST Reactor Vessel Internals Pre-Critical Vibration Visual Monitoring Program Ref.
(a): Project Procedure for Visual Inspection of Reactor Vessel Internals for SONGS 2 and 3. C-E Specification No.1370-RCE-413 (b):
CE-GQC Surveillance Trip Report dated The following items are to be considered during each evaluation of the subject This sheet shall be completed, signed, and attached to the data being program.
attained by the inspector. Details of verification of (1) through (7) below shall be recorded in Reference (b).
1.
Has the inspector obtained certification of his visual ability in accordance with Reference (a)?
2.
Has the inspector been certified to be technically qualified in accordance with Reference (a)?
3.
Is the inspector making adequate notations of the internals condition?
4.
Is the inspector adequately completing the data form in accordance withReference(a)?
5.
Is the inspector utilizing the current revision of Reference (a)?
6.
Is the inspector carrying out the examination in accordance with the requirements of lighting, distance, and angle specified in Reference (a)?
7.
Is the inspector verifying that he has adequate resolution in ac-cordance with the requirements of Reference (a)?
Signature /Date Page 35 of Specification No. 00000-RCE-413 As Modified By:
Specification No.1370-RCE-413 Page 6 of 6 Revision 00 r
e
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