ML20206D648

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Forwards Relief Request 88-08 Re ASME Code Section XI Requirement Re Safety Injection Accumulator Tanks.Relief Request 88-08 Supersedes Relief Request 88-06
ML20206D648
Person / Time
Site: McGuire, Mcguire  
Issue date: 11/08/1988
From: Tucker H
DUKE POWER CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8811170189
Download: ML20206D648 (6)


Text

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Dde1%r Company lla B Tas.c

?O Bar 33198 ike PresiJeM Chartone, N C 8242 Nuclear 1%fuction

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DUKEPOWER R

November 8, 1988 U.S. Nuclear Regulatory Consnission Attention: Document Control Desk L

W:shington, D.C.

20555 Subjects McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 ASME Code Section XI Requirements Relief Request No. 88-08 l

l Gsntlement j

By letter dated July 1, 1988. Duke transmitted a request for relief from ASME Code Ssetion XI Requirements pertaining to McGuire Nuclear Station's Unit 2 Safety Injection Accumulator Tanks. Subsequently, it has been determined that the same i

request for relief must also be submitted for the Unit 1 Safety Injection l

Accumulator Tanks. This subject was discussed with Mr. D. Hood (McGuire Project M: nager) of NRC ONRR and an agreement was reached to submit another request l

partaining to Lath Units 1 and 2.

Therefore, pursuant to 10 CTR 50.55a(g)(5)(iii) Duke is submitting for review and approval the attached Relisi Rsquest No. 88-08 to supersede Relief Request No. 88-06.

Relief Request No. 88-08 i

portains to McGuire's Unit 1 and 2 Safety Injection Accumulator Tanks.

l 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 l

R: quest No. 88-08 supersedes Relief Requet No. 88-06, no additional fea is nscessary.

Should there be any questions concerning this matter, please contact S.E. LeRoy at (704)373-6233.

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p Vary truly yours, i

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  • Ralief Request No. 88-08 November 8, 1988 Pcge 2 xc Mr. M.L. Ernst Deputy Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 t

Atlanta, GA 30323 Mr. Darl llood U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C.

20555 Mr. P.K. Van Doorn NRC Resident Inspector McGuire Nuc* ear Station l$

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U.S. Nuc1ccr R:gulctory Comiiccion

  • RalioY Request No. 88-08 November 8, 1988 Pcgo 3 bxc: A.F. Batts C.B. Cheezem II.E. Edurds R.L. Gill i

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U.S. Nuclear R:gulatory Commission November 8, 1988 DUKE POWER COMPANY McGUIRE NUCLEAR STATION, UNITS 1 AND 2 REQUEST FOR RELIEF FROM ASME CODE SECTION XI REQUIREMENT DETERMINED TO BE IMPRACTICAL RELIEF REQUEST NO. 88-08 1.

Component For Which Relief Is Requested:

A.

Namo and Number:

Safety Accumulator Tanks 1A, IB, IC. ID, 2A, 2B, 2C, and 2D B.

Function:

The accumulators at McGuire (S per unit) are pressure vessels filled with borated water and pressorized with nitrogen gas. During normal i

operation each accumulator is isolated from the Reactor Coolant system by two check valves in series.

One accumulator is attached to each of the cold legs of 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 1cvel may be adjusted either by draining to the reactor coolant drain tank, or by F

pumping borated water from the refueling water storage tank to the accumulator using the safety injection pumps. 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 + hem from pressures in excess of design pressure. The accumulat.n. are located within the Containment but outside of the secondary shield wall which protects them from missiles. The parameters of the accumulator tanks are as follows:

F o

Design Pressure, psig 700 o

Design Temperature, degrees-F 300 Operating Temperature, degrees-F 60-150 o

Normal Operating Pressure, psig 455 o

o Minimum Operating Pressure, psig 430 o

Total Volume, cubic feet 1350 each o

Minirne Water Volume, cubic feet 1075 each Volume of Nit rogen Gas, cubic feet 275 o

o Boric Acid Concentration, Nominal, ppm 2000 i

Relief Valve Setpoint, psig 700 o

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ASME III Code Class:

Equivalent Class 2 l

U.S. Nuclecr R:gulatory Commiccion

' Attachment Pcge 2 D.

Materials:

The accumulator tanks are carbon steel (SA 284) with clad welded Stainless Steci (SA-240) lining.

2.

ASMR Code Section XI Requircamnt That lias Been Determined To Be Impractical:

ASME Boiler and Pressure Vessel Section XI, 1980 Edition through Winter 1980 addenda Article IWC-2500-1. Item C01.010.051.

The code requires the inspection of one Shell to Upper llead wold and one Sho11 to Lownr 11ead wold to complete the equivalent of one vessel.

3.

nasis For Requesting Relief:

The ASME code requires that all of the velds associated with the subject tank be inspected during the 120 month ISI interval. The coda allows that welds be chosen at random from the total of 4 tanks as long as the welds collectively are equivalent to the total welds of one tank.

The Unit i and 2 Safety Injection Accumulator Tanks are designed such that the Shell to Lower llead Welds are inaccessible to prepare the surface for ultrasonic examination. The weld on each tank is located approximately one inch from where the support skirt is velded to the tank. This situation exists for all Unit 1 and 2 accumulator tanks.

4.

Alternative Testing:

Duke proposes to perform an additional Shell to Upper llead weld.

5.

Why The Alternate Proposed Testing Will Provide An Acceptabic Imvel Of Quality And Safety:

i The Safety Injection Accumulator Tank Shell to Upper llead welds have the same geometric design and thickness as the Shell to Lower llead welds. The Shell to Upper llead weld and Shell to Lower llead welds are identical in size, material, and 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.

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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 outage.

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