ML20147E606
| ML20147E606 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/15/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 3065, NUDOCS 7812210135 | |
| Download: ML20147E606 (31) | |
Text
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e ARKANSAS POWER & LIGHT COMPANY j
POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 (501) 371-4000
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December 15, 1978 I
i 1-128-3 Director of Nuclear Reactor Regulation ATTN:
Mr. R. W. Reid, Chief Operating Reactor Branch #1 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Sul lect: Arkansas Nuclear One - Unit 1 Docket No. 50-313 l
License No. DPR-51 Inservice Inspection Frogram (File:
3065)
Gentlemen:
In October,1977, we submitted our Inservice Inspection and Inservice Testing Programs which incorporated the 1974 ASME B&PV Code,Section XI through the Summer 1975 Addenda.
Your April 20, 1978, letter granted 4
interim approval, and on September 13, 1978, you requested additional in-formation in order to complete your evaluation.
Attached are responses to those items of the ISI Program which were not resolved during the meetings at Arkansas Nuclear One (ANO) on November 15 and 16,1978.
Inservice testing responses to open items will be provided by January 16, 1979.
l Very trul
- ours, 1
n C-'
Daniel
. Williams j
Manager, Licensing l
i DHW: ERG:ce i
Attachment 1
qp233W pl W;
y ca MEMDER MOOLE SOUTH UTluttES SYSTEM l
i 1
RESPONSES TO NRC QUESTIONS' i
ON ISI RELIEF REQUESTS l
l Question #1 Can full volumetric examinations be performed in accordance with' the provisions of Appendix I, Ultrasonic Examination for all Class-1 and 2 vessels and Article V of ASME,Section V for all Class 1 and 2_ piping? Discuss examination alternatives considered to supplement examinations in which scan is limited by geometry or obstructions (i.e., examinations from o'ne side only, access.not available for transducer movement to accomplish full volumetric examination, pipe supports in the way, etc.).
Also, discuss ex-amination alternatives for supplementing piping inspections where P vee path calibrations are used and full volumetric examinations 2
are not achieved.
Response
AP&L's program for inspections includes only Class 1 & 2 welds that are accessible for examination in accordance with applic-able codes.. Relief requests have been made on all welds iden-tified as inaccessible.
An attached marked-up set of inspection isometrics identifies all Class 1 & 2 welds scheduled for exam-ination during the inspection interval.
These isometrics'do not include longitudinal welds on pipe and fittings although they are scheduled.
Also included are scope drawings of all Class 1 & 2 NDE examinations.
Where configuration or adjacent parts of the component are such that scanning from both sides is not practical, this fact is to be recorded on the data sheet and reported as a limited examin-ation in compliance with Article I-5121.
In the case of the reactor vessel where RT is prevented due to the radiation level of the vessel, additional scanning of the area of interest, using a transducer with an incident angle other than 45 and 60 degrees can reduce or eliminate the area previously excluded.
In the case of piping where k vee path calibration are used, RT 2
examination may be performed in some cases with better success
.than the UT examination. Where volumetric examinations cannot
L -
be performed on all or part of the weld, a supplemental MT or PT surface examination could be performed on accessible portions of the part to be examined.
Question #2:
Provide information discussing how the examination required for item B.S.6, Table IWB-2600, volumetric examination of pump casing welds, will be accomplished.
Response
.The examination of reactor coolant pump casing welds by means of UT is, at present, beyond the " State of the Art".
The use of RT is not practical, since the radioactive source must be placed inside the reactor coolant pumps. There is no means of doing this remotely,
.thus such an examination would expose personnel involved to danger-ously high radiation levels.
Therefore, a relief request on this item is to follow at a later date.
Question #3:
Are the augmented inspection requirements stated in paragraph 4.1.5 of the Technical Specifications for high energy lines outside of the containment included in the ISI program? Are the frequency and ex-tent of the examination scheduled as required?
Response
The examination of the welds in these lines is included in the ISI program.
The schedule for their examination is also included.
This question was resolved at a meeting with members of your staff at AN0 on November 15, 1978.
Question #4:
Provide justification for the exclusion of the following pumps from the operational readiness testing program:
a.
Fuel Transfer Pumps for the emergency diesels b.
Emergency Feedwater Pumps c.
Pumps for chemical additior,s
Response
Justification for the exclusion of items (a) and'(c) was provided to the NRC at the meeting of 11/15/78 at ANO.
The testing of the steam driven emergency feedwater pump is per Operating Procedure 1106.6.
This'p ocedure is being revised to include the same re-quirements asSection XI of t'he ASME B&PV Code through Summer 1975 Addenda.
The pump will therefore not be included in Section XI-r Pump and Valve Program but will be done to Section XI requirements as specified in the referenced Operating Procedure.
Question #5:
Provide justification for not includincj measurenent of flow as an inservice test quantity;for Unit 1 pumps.
n
Response
All Unit 1 pumps which require inservice testing except service water pumps, are connected to fixed resistance systems.
For these pumps, the measurement of the pressure differential across-.the pumps pro-vides the required information.
Flow measuring devices will be in-e stalled in the service water system during our third refueling out-age scheduled for March 1,1979.
After this installation, flow measurement.will be included as a test quantity for the service water pumps.
This question was discussed and resolved at a meeting with members of your staff at ANO on November 15, 1978.
Question #6:
Identify those systems classified as Class 2 pursuant to Regulatory Guide 1.26 which have been exempted from examination by ASME B&PV Code,Section XI, paragraph IWC-1220.
Clarify the pressure testing
. I to be performed for these exempt components and the respective ' test frequency.
Response
The systems classified as Class 2 per Regulatory Guide 1.26 to be pressure tested in accordance with IWC-2412(a) relating to exempted components are identified on attached P&ID's as Class 2E systems.
These systems will be tested in accordance with IWC-5000 and IWA-5000 at the pressures indicated on the P&ID's unless subsequent relief is obtained.
The test frequency will be in accordance with i
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IWC-2412(a).
Please' note, Regulatory Guide 1.26 does not address all Class 2 components.
For example, gas-filled systems, radioactive waste management-systems, containment penetrations, and tubing are not addressed by' Regulatory Guide'1.26 and are not included in this testing program.
- Question #7:
Identify those sytems which you have classified as Class 3 pursuant.
to Regulatory Guide 1.26 for inservice inspection purposes.. Clarify the testing which will be performed for those systems.
For the Class 3 systems that are burieJ, identify and provide information on how 'the testing will be conducted.
Response
The systems classified as Class 3 per Regulatory Guide -1.26, 'are identified on the attached P&ID's.
These systems will be_ tested in accordance witn IWA-5000, IWD-5000 and IWD-2600 by the end of each inspection interval except those areas where subsequent relief is obtained.
In addition,these systems will be examined in accordance with IWA-5240 and IWD-2600 while in operation or during inservice testing by the end of every one-third of each inspection interval.
Portions of the service water system have been identified as being buried.
This system cannot be pressure tested since valves pro-vided for isolation were not designed for pressure testing.. A request for relief in this area will follow at a later date.
Question #8:
This question was changed at the meeting at ANO on November 15, 1978, since the relief request was based on radiation exposure problems and not material problems.
The question was restated as:
Provide the following information regarding the core flood nozzle safe-end welds:
a) The shielding to be used b) The estimated man-rem exposure.
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Response
'The examination of the core flood nozzle safe-end weld requires the set-up and removal of scaffolding and the removal and re-installation of insulation around the ~ core flood line.
This work would.be.done in the area between the reactor vessel and the. pri--
mary shield wall.
The only shielding available is the insulation on the reactor vessel.
The estimated radiation exposure is six man-rems per nozzle, making examination impractical on an ALARA
- basis,
- ' Question #9:
The attached sketches for relief reques't;for item B.4.5, Category B-Js pipe welds were not included in the' package ~for review.
Pro-vide either the sketches or other drawings showing the accessibility.
limitations.
Can a surface examination be performed for the high pressure injection welds or core flood line welds? Can the pipe supports for the core flood lines be removed to the extent neces-sary to perform the required examination without endangering.the remainder of the system?
Response
The' requested sketches were provided at the meeting at ANO on November 15, 1978.
The high pressure injection line welds in question, are located approximately 3h - 4 feet inside the con-tainment wall and are accessible only through a 3/4 inch gap be-tween the pipe and the penetration.
There is, therefore, no means of visually examining these welds.
The core flood lines are not accessible during normal operation.
We cannot determine the feas-ibility of removing pipe supports or doing a surface examination until our next outage'which is scheduled for March 1,1979.
This approach was discussed with members of your staff'at the meeting at ANO on November 15, 1978.
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