ML18139B821

Forwards Response to 820218 Request for Addl Info Re Inservice Insp Program.Drawing of Branch Nozzle Connection Weld Encl

ML18139B821
Person / Time
Site:	Surry
Issue date:	03/25/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
111, NUDOCS 8203300145
Download: ML18139B821 (4)

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,, VIRGINIA 23261 ...

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R.H.LEASBURO March 25, 1982

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Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation NO/RMT:acm Attn: Mr. Steven A. Varga, Chief Docket Nos. 50-280 Operating Reactors Branch No. 1 50-281 Division of Licensing License Nos. DPR-32 U. S. Nuclear Regulatory Commission DPR-37 Washington, D. C. 20555 Gentlemen:

This letter is provided in response to your request for additional information dated February 18, 1982 relative to Inservice Inspection Program for Surry Power Station. Enclosures 1 and 2 of this letter provide the information requested.

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R.H. Leasburg

Enclosures:

1. Inservice Inspection Program - Surry Unit One

2. Inservice Inspection Program - Surry Unit Two

3. Figure 1 4ool

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• Enclosure 1 Serial No. 111 INSERVICE INS*PECTION PROGRAM SURRY UNIT ONE

1. Questions A, B, C.

In review of radiation surveys conducted by the site Health Physics group, the regenerative heat exchanger is an area of fluctuating radiation levels. When the unit is in operation, there are several points that the levels are equal to or greater than 20 Rem. During the steam generator replacement project and during refueling outages these levels dropped to 6-7 Rem on contact.

Eyen if these levels were to drop in half through flushing and shielding, the time needed to erect scaffolding, remove insulation, cleaning, perform examinations and restore the installation could take a total of 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for the examinations of 1/2" long portions of twelve welds. It is still felt that personnel exposure to complete these exams is excessive particularly when the examination is to establish the continued integrity of the vessel in a system in which all the piping welds are exempt from examination by IWC-1220 (D).

Question D.

As shown on Surry Unit One flow diagrams 11448-FM-103A and 11448-FM-105C, there are two check valves 1312A and 1310 on line 3" CH-1. Based on ASME Boiler and Pressure Vessel Code Section XI 1974 Edition up to and including summer of 1975 addenda section IWB 1220 paragraph (2), the second check valve in a series constitutes the end of the Class 1 boundary.

2. For Item B4.5 the total number of welds where ultrasonic examination cannot be performed on 100% of the weld and heat affected zone and where surface examination will be done as a supplement is 14 or 3.5%. For item B4.5 there are also 12 longitudinal electroslag welds in the Reactor Coolant Pipe.

These welds will be done surface only due to thickness and material. For B4.6 the total is 5 or 100% of welds in this category.

3. For Class 2 circumferential welds item C2. 1 the total number of welds where ultrasonic examination cannot be performed on 100% of the weld and heat affected zone and where surface examination will be done as a supplement is determined on an individual weld basis when examined since these welds were not examined during preservice inspection. However, this relief will not be required when Surry Unit Ill updates to the later code Edition *

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• Enclosure 2 Serial No. Ill INSERVICE INSPECTION PROGRAM SURRY UNIT TWO I. Questions A, B, C. (

In review of radiation surveys conducted by the site Health Physics group, the regenerative heat exchanger is an area of fluctuating radiation levels. When the unit is in operation, there are several points that the levels are equal to or greater than 20 Rem. During the steam generator replacement project and during refueling outages these levels dropped to 6-7 Rem on contact.

Even if these levels were to drop in half through flushing and shielding, the time needed to erect scaffolding, remove insulation, cleaning, perform examinations and restore the installation could take a total of 8 to 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> for the examinations of 1/2" long portions of twelve welds. It is still felt that personnel exposure to complete these exams is.excessive particularly when the examination is to establish the continued integrity* of the vessel in a system in which all the piping welds are exempt from examination by IWC-1220 (D).

Question D.

Any examination method, liquid penetrant, ultrasonic or radiography would still result in extended exposure if examining 1/2 11 of each weld versus 100%

of one weld.

The regenerative heat exchanger is a Class I component for Surry Unit Two based on flow diagram 11548-FM-103 and 1154-FM-IOSC which shows line 3" CH-301 has a check valve 2312A, then a normally open valve 2310 then through the regenerative heat exchanger to check valve 2312B. Based on ASME Boiler and Pressure Vessel Code Section XI 1974 Edition up to and including summer of 1975 addenda section IWB-1220 paragraph (2) the second check valve in series constitutes the end of the Class I boundary.

2. Attached is a sketch of the joint configuration of the nozzle to vessel weld. Due to configuration and geometry an ultrasonic examination is impractical.

3. For Item B4. 5 the total number of welds where ultrasonic examination cannot be performed on 100% of the weld and heat affected zone and where surface examination will be done as a supplement is 10 or 2.5%. For item B4.5 there are also 12 longitudinal electroslag weld in the Reactor Coolant pipe, These welds will be done surface only due to thickness and material. For item B4.6 the total is 5 or 100% of welds in this category.

4. For Class 2 circumferential welds item C2. I the total number of welds where ultrasonic examination cannot be performed on 100% of the weld and heat affected zone and where surface examination will be done as a supplement is determined on an individual weld basis when examined since these welds were not examined during preservice inspection. However, this relief will not be required when Surry Unit #2 updates to the later code Edition.

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FIGURE ONE BRANCH NOZZLE CONNECTION WELD CENTERLINE NOZZLE NOZZLE FORGING REGENERATIVE -HEAT EXCHANGER

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