ML20235U216
| ML20235U216 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/28/1989 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20235U200 | List:
|
| References | |
| NUDOCS 8903090100 | |
| Download: ML20235U216 (3) | |
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" DUKE POWER GowrAxy l
P.O. box 33180 CHARLOTTE. N.C. 28242 HAL B. TUCKLt nos casesoner, JO4) 373-4531 -
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scossaa enooveno, February 28, 1989 WFORMABON U.S. Nuclear Regulatory Commission g,3____
Document Control Desk Washington, D.C.
20555
Subject:
Duke Power Company e
Oconee Nuclear Station Docket Nos. 50-269, -270, -287 McGuire Nuclear Station Docket Nos. 50-369, -370 Catawba Nuclear Station Docket Nos.. 50-413, -414 Gentlemen:
Pursuant to 10 CFR 50.55a(a)(3), we request that NRC approve Duke. Power's use of Code Case N-356: Certification period for Level III NDE pe.rsonnel.
The reason
_this request is being submitted at this time is the result of NRC's current review of McGuire's ISI program in which you noted that formal approval for use of the code case had not been requested. This code case is currently being used at Duke and was noted in NRC Inspection Report 50-369/84-41 and 50-370/84-38.
In the inspection
- report, it was identified as an Inspector Follow-up.
Item (370/84-38-03), and was resolved to the NRC's satisfaction and closed out in Inspection Report 50-369/85-37 and 50-370/85-38.
Although this code case has not listed for use under Regulatory Guide 1.84, 1.85, or 1.147, it has been been adopted in the 1983 winter addenda of ASME Section XI, which has been approved by Based on these facts, we believe this code case should be approved for use NRC.
at Duke's nuclear plants.
A copy af the code case is attached for your use.
Should there be any questions concerning this matter, please contact S.E. LeRoy at (704) 373-6233.
Very truly yours, 7(
Hal B. Tucker SEL/388/sel Attachment 5
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February 28, 1989 Page 2 10%
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I xc: Mr. M.L. Ernst, Acting Regional Administrator U.S. Nuclear Regulatory Conthission
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Region II
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.101 Marietta St., NW, Suite 2900 Atlanta, Georgia 30323 Mr. P.K. Van Doorn NRC Resident Inspector McGuire Nuclear Station Mr. W.T. Orders NRC Resident Inspector Catawba Nuclear Station Mr. P.H. Skinner NRC Resident Inspector Oconee Nuclear Station Mr. Darl Hood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Ms. Helen Pastis U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
20555 Dr. K. Jabbour U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.
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-y CASE J!7ORNMT!0h' N-356 CASES OF A5ME BOILER AND PRESSURE YESSEL CODE Approvel Date: July 18,1982 See Numere Index for expiratien and eny reaffirmation Ceres.
Case N 366 Certification Period for Level ill NDE Personnel Section XI, Divisions 1,2, and 3 Inquiry: 16 it permissible to extend the certification period for Level 111 NDE personnel to five years?
Reply: It is the opinion of the Committee that the certification period for Level ill NDE personnel may be extended to five years.
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PC Box 33198 L a Pen.Mt Charlotte, N C 28242 b lear ?m.wtin t ~% 1,~34 Ui DUKEPOWER W ORM M November 8, 1988-U.S. Nuclear Regulatory Commission
' Attention: Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station, Units-1 and 2 Docket Nos. 50-369 anci 50-370 ASME Code Section XI Requirements l
Relief Request No. 88-08 Gentlemen:
By letter dated July 1,1988, Duke transmitted a request for relief from ASME Code Section XI Requirements pertaining to McGuire Nuclear Station's Unit 2 Safety Injection Accumulator Tanks. Subsequently, it has beea determined that the sama request for relief must also be submitted for the Unit 1 Safety Injection Accuaralator Tanks. This subject was discussed with Mr. D. Hood (McGuire Project Manager) of NRC ONRR and an agreement was reached to submit another request pertaining to both Unite 1 and 2.
Therefore, pursuant to 10 CFR I
50.55a(g)(5)(iii), Duke is submitting for re*.riew and approval the attached Relief Request No. 88-08 to supersede Relief Request No. 88-06~.
Relief Request No. 88-08 pertains to McGuire's Unit 1 and 2 Safety Injection Accumulator Tanks.
Pursuant to 10 CFR 170.3(y), 170.12(c), and 170.21, an application fee of $150.00 was submitted for McGuire Relief Request No. 88-06; therefore, since Relief Request No. 88-08 supersedes Relief Requet No. 88-06, no additional fee is nece:ssary.
Should there be any questions concerning this matter, please contact S.E. LeRoy at (704)373-6233.
f Very truly yours,
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n Hal B. Tucker SEL/ relief /sel
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Relief Request No. 88-08 c
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Movember 8, 1983 L
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')1FORNE0Lp Page 2 xc Mr. M.L. Ernst Deputy Regional Administrator Region II U.S. Nuclear Regulatory Comission 101 Marietta St., !N, Suite 2900 Atlante.-, GA 30323
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Mr. Darl Hood U.S. Nuclear Regulatory Comission
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Office of Nuclear Reactor Regulation Washington, D.C.
20555 Mr. P.K. Van Doorn NRC Resident. Inspector
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McGuire Nuclear Station s
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' U.S. Nuclear Regulatory Commission November 8, 1988
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DUKE POWER COMPANY McGUIRE NUCLEAR' STATION, UNITS 1 AND 2 REQUEST FOR RELIEF FROM AS.ME CODE SECTION XI REQUIREMENT DETERMINED TO BE IMPRACTICAL l.
RELIEF REQUEST NO. 88-u8-1.
Component For Whiyt Relief Is Requested:
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Name and Number:
Safety Accumulator Tanks 1A, 1B, 10, 1D, 2A, 2B, 2C, and 2D B.
Tunction:
The accunn:lators at 8:Guire (4 per unit) are pressure vessels filled with borated water and pressurized with nitrogen gas. During normal operation each accumulator is isolated from the Reactor Coolant system by two check valves in series.
One accumulator is attac.hed to each of the cold legs c,1 the Reactor Coolant system. Connections are provided for remotely adjusting the level and boron concentration of the borated water in each accumulator during normal operation as required. Accumulator water level may ba adjusted either by draining to the reactor coolant drain tank, or by pumping borated water from the rr. fueling water storage tank to the accumulator using the safety injaction pumpn Accumulator pressure is provided by a supply of nitrogen gas, within their own volume, and can be adjusted as required during normal operation; however, the accumulators are normally isolated from the source of this nitrogen supply. Gas relief valves on the accumulators protect them from~
pressures it. excess of design pressure. The accumulators are located I
within the Containment but outside of the secondary shield vall which I
protects them from cissiles. The parameters of the accumulator tanks are as follows:
o Design Pressure, psig 700 o
Design Temperature, degrees-F 300 o
Operating Temperature, degrees-F 60-150 Normal. Operating Prnssure, psig 455 o
Minimum Oretating Pressure, psig 430 o
o Total Vohs.e, cubic feet 1350 each o
Minimum Water Volume, cubic feet 1075 each o
Volume of Nitrogen Gas, cubic feet 275 o
Boric Acid Concentration, Nominal, ppm 2000 o
Relief Valve Setpoint, psig 700 C.
ASME III Code Class:
Equivalant Class 2 l
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Materials:
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The accumulator tanks are carbon steel (SA-284) with clad welded Stainless Steel (SA-240) lining.
2.
ASME Code Secuan XI Requirer.ent That Has Been Determined To Be Impractical:
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ASME Boiler and Pressure Vessel Section XI, 1980 Edition through Winter 1980 j
addenda, Article IWC-2500-1, Item C01.010.051.
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The code requires the inspection of one Shell to Upper Head weld and one Shell to Lower Head weld to complete the equivalent of one vessel.
3.
Basis For Requesting R211ef:
The ASME code requires that all of the welds associated with the subject tank be inspected during the 120 month ISI interval. The code allows that
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welds be chosen at t'andom from the total of 4 tanks as icng as the welds j
collectively are equivalent to the tctal welds of one tank, The Unit 1 and '2 Safety Injection Accumulator Tanks tre designed such that the Shell to Lower Head Welds are inaccessible to prepare the surface for
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ultrasonic examination. The weld on each teak is located approximate}v one 4
inch from t:here the r,uppott skirt is welded to the tank. This situation exists for all Unit 1 and 2 accumulator tanks.
4.
Alternative Testing:
Duke proposes to perfonn an additional Shell to Upper Head weld.
5.
Why The Alternate Proposed Testing Will 1rovide An Acceptable Level Of Quality And Safety:
The Safety Injection Accumulator Tank Shell to Upper Head welda have the same ge.ametric design and thickness as the Shell to Lower Head welds. The Shell to Upper Head weld and Shell to Lower Read welds are identical in size, materiel, snd type of weld. The results of the alternate testing should be indicative of the conditions that exist for the welds that are inaccessible.
These specific welds are covered by the McGuire ISI Plan.
6.
Implementation:
The Unit 2 inspection was perfrmed during the Unit 2, fourth refueling outage. The Unit 1 inspection will be performed during the current Unit 1, fifth refueling outap..
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