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{{#Wiki_filter:o e
{{#Wiki_filter:o e
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Duquesne LkJ1t                                                           Telephone (412) 393-6000 0 Eox4 Shippingport. PA 15077 0004 June 16, 1987 U. S. Nuclear Regulatory Commission Attn:       Document Control D6sk Washington, DC                 20555   ,
Duquesne LkJ1t Telephone (412) 393-6000 0 Eox4 Shippingport. PA 15077 0004 June 16, 1987 U. S. Nuclear Regulatory Commission Attn:
Document Control D6sk Washington, DC 20555


==Reference:==
==Reference:==
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66                                         l CH-E-1 and CH-E-2 Relief Request Gentlemen:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 l
Attached is a request for relief from certain ASME Section                           XI inspection requirements for the Seal Water Heat Exchanger                       (CH-E-1)
CH-E-1 and CH-E-2 Relief Request Gentlemen:
The requests and the Non-Regenerative Heat Exchanger (CH-E-2).
Attached is a
provide the code requirements, Nmendment 22 inspection requirements, a basis for requesting relief and a proposed alternate examination.
request for relief from certain ASME Section XI inspection requirements for the Seal Water Heat Exchanger (CH-E-1) and the Non-Regenerative Heat Exchanger (CH-E-2).
code requirements listed in the relief request have been The determined to be impractical for Beaver Valley, Unit No. 1 in accordance with 10 CFR 50.55a(g)(5)(iii).
The requests provide the code requirements, Nmendment 22 inspection requirements, a
Attached is a check in the amount of $150.00 for payment of the application fee in.accordance with 10 CFR 170.
basis for requesting relief and a proposed alternate examination.
The code requirements listed in the relief request have been determined to be impractical for Beaver
: Valley, Unit No.
1 in accordance with 10 CFR 50.55a(g)(5)(iii).
check in the amount of $150.00 for payment of the Attached is a
application fee in.accordance with 10 CFR 170.
Very truly yours, 1
Very truly yours, 1
                                                                  ]   .                              ,
]
                                                              . d. Siebe Vice President, Nuclear Attachment 8707060446 870616 PDR         ADOCK 05000334 G                           PDR BEc o alcateg.                               ,4 0Y ,I 80
. d. Siebe Vice President, Nuclear Attachment 8707060446 870616 PDR ADOCK 05000334 PDR G
:# S??f y'f $lSo.oo                                 j
BEc o alcateg.
,4 0,I Y
80
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      , Beaver Valley Power Station, Unit No. 1 Docket No'. 50-334, License No. DPR-66 CH-E-1 and CH-E-2 Relief Request Page 2 cc: Mr. F. I. Young, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station                   i Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA   19406 Mr. Peter S. Tam U. S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
, Beaver Valley Power Station, Unit No. 1 Docket No'. 50-334, License No. DPR-66 CH-E-1 and CH-E-2 Relief Request Page 2 cc:
            - Mail'Stop 316 Addressee only Director, Safety Evaluation & Control Virginia' Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 l
Mr. F. I. Young, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station i
Shippingport, PA 15077 U.
S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U.
S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555
- Mail'Stop 316 Addressee only Director, Safety Evaluation & Control Virginia' Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 l


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1 Cil-E-1 and Cil-E-2 Relief Requests I
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Cil-E-1 and Cil-E-2 Relief Requests I


1 A
1 A
Line 47: Line 58:
Non-Regenerative Heat Exchanger (CH-E-2)
Non-Regenerative Heat Exchanger (CH-E-2)
Section XI Requirement (74S75)
Section XI Requirement (74S75)
Table IVC-2520,     Category C-A, pressure-retain!       welds in pressure vessels, . requires a minimum of 20% of each           .ircumferential veld, uniformly distributed among three areas around th< vessel circumference, be volumetrically examined each interval.
Table IVC-2520, Category C-A, pressure-retain!
welds in pressure vessels,. requires a minimum of 20% of each
.ircumferential veld, uniformly distributed among three areas around th< vessel circumference, be volumetrically examined each interval.
Amendment 22 to Operating License No. DPR 66 '
Amendment 22 to Operating License No. DPR 66 '
                ' Amendment 22 obtained relief       from   the code required volumetric examination on the Seal Water Heat Exchanger shell-to-flange and head-to-shell velds. The alternative examinations were surface and visual inspections.
' Amendment 22 obtained relief from the code required volumetric examination on the Seal Water Heat Exchanger shell-to-flange and head-to-shell velds. The alternative examinations were surface and visual inspections.
Basis for Relief During the summer of 1986 Refueling Outage, the radiological conditions in the areas of the heat exchangers, CH-E-1 and CH-E-2, were measured and found to be 300-500 mr/hr in the immediate working area with hot spots of 3R/hr and 7R/hr, respectively.         These radiation levels-are expected to increase throughout the service life of the components since by their function and design, they are susceptible to corrosion and wear product buildup.
Basis for Relief During the summer of 1986 Refueling Outage, the radiological conditions in the areas of the heat exchangers, CH-E-1 and CH-E-2, were measured and found to be 300-500 mr/hr in the immediate working area with hot spots of 3R/hr and 7R/hr, respectively.
These radiation levels-are expected to increase throughout the service life of the components since by their function and design, they are susceptible to corrosion and wear product buildup.
The following conditions made the Section XI and Amendment 22 required inspections impractical:
The following conditions made the Section XI and Amendment 22 required inspections impractical:
l
l 1.
: 1. The manrem estimate for the personnel to prepare, inspect, and         l reinsulate these components is projected to be 18.75 manrem. This estimate is based on working space dose rates and estimated work durations as noted on the attached manrem estimate. This estimate represents an     optimum   work   schedule   and any difficulties encountered would increase the dose.
The manrem estimate for the personnel to prepare, inspect, and l
: 2. The component geometry limits the inspection of the endcap-to-vessel veld to one side only.     Inspection from the endcap side is not possible volumetrically and access from the vessel side is limited by the nozzles and supports for Veld #1 (sFovn on the attached drawings). The restrictions to Veld #2 are similar to the limitations described for Veld #1 since the flange side cannot be inspected due to the flange geometry.     These restrictions make it virtually impossible to     obtain   meaningful   results from the volumetric examination of these two velds.
reinsulate these components is projected to be 18.75 manrem. This estimate is based on working space dose rates and estimated work durations as noted on the attached manrem estimate. This estimate represents an optimum work schedule and any difficulties encountered would increase the dose.
          ' Alternate Examination Visual inspection for leakage during the performance of the system leakage examinations, t
2.
The component geometry limits the inspection of the endcap-to-vessel veld to one side only.
Inspection from the endcap side is not possible volumetrically and access from the vessel side is limited by the nozzles and supports for Veld #1 (sFovn on the attached drawings). The restrictions to Veld #2 are similar to the limitations described for Veld #1 since the flange side cannot be inspected due to the flange geometry.
These restrictions make it virtually impossible to obtain meaningful results from the volumetric examination of these two velds.
' Alternate Examination Visual inspection for leakage during the performance of the system leakage examinations, t


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Latest revision as of 06:55, 3 December 2024

Forwards Request for Relief from Certain ASME Section XI Insp Requirements for Seal Water HX & Nonregenerative Hx.Fee Paid
ML20234C391
Person / Time
Site: Beaver Valley
Issue date: 06/16/1987
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8707060446
Download: ML20234C391 (7)


Text

o e

'Ab?

Duquesne LkJ1t Telephone (412) 393-6000 0 Eox4 Shippingport. PA 15077 0004 June 16, 1987 U. S. Nuclear Regulatory Commission Attn:

Document Control D6sk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 l

CH-E-1 and CH-E-2 Relief Request Gentlemen:

Attached is a

request for relief from certain ASME Section XI inspection requirements for the Seal Water Heat Exchanger (CH-E-1) and the Non-Regenerative Heat Exchanger (CH-E-2).

The requests provide the code requirements, Nmendment 22 inspection requirements, a

basis for requesting relief and a proposed alternate examination.

The code requirements listed in the relief request have been determined to be impractical for Beaver

Valley, Unit No.

1 in accordance with 10 CFR 50.55a(g)(5)(iii).

check in the amount of $150.00 for payment of the Attached is a

application fee in.accordance with 10 CFR 170.

Very truly yours, 1

]

. d. Siebe Vice President, Nuclear Attachment 8707060446 870616 PDR ADOCK 05000334 PDR G

BEc o alcateg.

,4 0,I Y

80

  1. S??f y'f

$lSo.oo j

, Beaver Valley Power Station, Unit No. 1 Docket No'. 50-334, License No. DPR-66 CH-E-1 and CH-E-2 Relief Request Page 2 cc:

Mr. F. I. Young, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station i

Shippingport, PA 15077 U.

S. Nuclear Regulatory Commission Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 Mr. Peter S. Tam U.

S. Nuclear Regulatory Commission Project Directorate No. 2 Division of PWR Licensing - A Washington, DC 20555

- Mail'Stop 316 Addressee only Director, Safety Evaluation & Control Virginia' Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection Pennsylvania Dept. of Environmental Resources P.O. Box 2063 Harrisburg, PA 17120 l

l s

J l

4 1

1 Cil-E-1 and Cil-E-2 Relief Requests I

1 A

Components Seal. Vater Heat Exchanger (CH-E-1)

Non-Regenerative Heat Exchanger (CH-E-2)

Section XI Requirement (74S75)

Table IVC-2520, Category C-A, pressure-retain!

welds in pressure vessels,. requires a minimum of 20% of each

.ircumferential veld, uniformly distributed among three areas around th< vessel circumference, be volumetrically examined each interval.

Amendment 22 to Operating License No. DPR 66 '

' Amendment 22 obtained relief from the code required volumetric examination on the Seal Water Heat Exchanger shell-to-flange and head-to-shell velds. The alternative examinations were surface and visual inspections.

Basis for Relief During the summer of 1986 Refueling Outage, the radiological conditions in the areas of the heat exchangers, CH-E-1 and CH-E-2, were measured and found to be 300-500 mr/hr in the immediate working area with hot spots of 3R/hr and 7R/hr, respectively.

These radiation levels-are expected to increase throughout the service life of the components since by their function and design, they are susceptible to corrosion and wear product buildup.

The following conditions made the Section XI and Amendment 22 required inspections impractical:

l 1.

The manrem estimate for the personnel to prepare, inspect, and l

reinsulate these components is projected to be 18.75 manrem. This estimate is based on working space dose rates and estimated work durations as noted on the attached manrem estimate. This estimate represents an optimum work schedule and any difficulties encountered would increase the dose.

2.

The component geometry limits the inspection of the endcap-to-vessel veld to one side only.

Inspection from the endcap side is not possible volumetrically and access from the vessel side is limited by the nozzles and supports for Veld #1 (sFovn on the attached drawings). The restrictions to Veld #2 are similar to the limitations described for Veld #1 since the flange side cannot be inspected due to the flange geometry.

These restrictions make it virtually impossible to obtain meaningful results from the volumetric examination of these two velds.

' Alternate Examination Visual inspection for leakage during the performance of the system leakage examinations, t

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