ML19326A461
| ML19326A461 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/09/1976 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| References | |
| 146, NUDOCS 8002040629 | |
| Download: ML19326A461 (8) | |
Text
.
1,1C e'uRu 195 U.S. NUCLE AR REGULATORY 9MMISGloN OoCKET NUMIC R f Q 3 y fp
- a. t.a NRC DISTRIBUTION Fon PART 50 DOCKET MATERIAL To:
Mr Rusche-FROM: Toledo-Edison Co oATE oF DoCUM T Toledo, Ohio L E Roe DATE RECEIVED 1
ILETTER O NoTonl2 E D PROP INPUT FORM NUMBER OF CCPtES Rf CCtVCD Wo R IGIN AL
$UNC LA03f R E D CCoPY one signed 0;Sc r.4 P Tio N ENCLoSU R E Ltr trans the following:
Addl info concerning surveillance requirements covered by Section XI of the ASME Boiler &
Pressure Vessel Codes......
PLANT NAME:
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Docket No. 50-346 2
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Serial No. 146
i (4191 259-5242 November 9, 1976 N
Pa Mr. Benard C. Rusche, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Con: mission Washington, D.C.
20555
Dear Mr. Rusche:
The draft technical specifications for the Davis-Besse Nuclear Power Station Unit i presently under review by the Applicant and the NRC references 10 CFR 50, Section 50.55 a (g) for all surveillance require-ments covered by Section XI of the ASME Boiler and Pressure Vessel Code.
As amended February 12, 1976, effective March 15, 1976, 10 CFR 50, Section 50.55 a (g) requires that "... components (including supports) which are classified as ASME Code Class 1, Class 2, and Class 3 shall meet the requirements set forth in Section XI of editions of the ASME Boiler and Pressure Vessel Code and Addenda that become effective...,
to the extent practical withic the limitations of design, geometry and materials of construction of the components."
10 CFR 50.55 a (g) also states that:
"The initial in-service exam-ination conducted during the first 40 months shall comply with the requirements in the edition of the code and addenda in effect no more than 6 months prior to the date start of facility commercial operation,"
and "The initial in-service tests of pumps and valves for assessing operational readiness and system pressure tests conducted during the first 20 months shall comply with those requirements in editions of the code and addenda in effect no more than 6 months prior to the start of facility commercial operation." For Davis-Besse Nuclear Power Station Unit 1 the code in effect 6 months prior to the start of facility com-mercial operation is taken to be the 1974 edition of Section II of the ASME Boiler and Pressure Vessel Code through the Summer 1976 addenda which for purposes of this letter will be referenced simply as the
" Code".
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"/11A lI t 2.5 THE TOLECO EDISCN CCMPANY EDISCN PLAZA 300 MADISON AVENUE TCLECC, CHIO 43S52
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. 10 CFR 50.55 a (g) also provides that:
"If the licensee has determined that conformance with certain code requirements is impractical for his faqility, tne licensee shall notify the Commission and submit infor-mation to support his determination." Further the Commission will evaluate this information and may grant relief as it determines is appropriate.
The purpose of this letter is to outline the program which the Applicant is preparing to comply with the requirements of 10 CFR 50.55 a (g) and to request written relief'from the Commission for performance of any further Section XI requirements during the initial in-service inspection and testing periods.
(40 months and 20 months respectively)
The following articles of Section XI represent our compliance with 10 CFR 50.55a (g).
1)
Welds in piping and their supports per the following:
a) Class 1 IS 200 b) Class 2 Subsection IWC c) Class 3 Subsection IWD 2)
Pumps Per Subsection IWP Classes 2 & 3 3)
Valves Per Subsection IWV Classes 1, 2 & 3 la.
The Davis-Besse Unit 1 project committed to pre-service and in-service inspect in accordance with the 1971 edition of Section XI of the ASME Boiler and Pressure Vessel Code through the Winter 1971 l
Addenda. The Class 1 pre-service examination has been performed in accordance with the 1971 edition of Section XI through the Winter j
1971 Addenda. The in-service inspection on Class 1 systems for the life of the plant will be performed in accordance with the 1971 editon of Section XI through Winter 1971 Addenda.
4 2
lb.
Class 2 welds in essential systems 2h" nominal size and larger will be inspected in accordance with Subsection IWC of the Code.
(1974 edition through Summer 1976 Addenda). The welds that will be inspected are in the areas where pipe breaks were postulated due to high stress concentrations as outlined in NRC Branch Technical Position MEB 3-1 and U.S. NRC Regulatory Guide 1.46, and Section XI Article, IWC 1220. Other' areas where pipe breaks were not postulated will not be volumetrically inspected.
I All Class 2 penetration welds 2h" nominal size and larger will be
. inspected in accordance with Subsection IWC of the Code. The inspection schedule for essential and penetration welds will be in accordance with IWC-2412 Inspection Program B in the Summer 1976 Addenda, during the first 40 month interval. Exceptions which must be taken on Class 2 systems are the following:
-~
1.
Schedule 10 penetration piping on 12 penetrations cannot be dressed for Volumetric examination without violating minimum a
wall thickness requirements since the material thickness is under 1/2".
These welds will be surface examined.
2.
Inaccessible welds which require plant modification for either volumetric or surface examination will not be inspected.
3.
Welds in moderate energy systems will not be inspected.
Ic.
Class 3 components will be hydrotested or visually examined on Systems 2 " and larger per the code requirements of IWD-5000, to the extent practical within the limitations of design, geometry and materials of construction of the component.
- 2. defines the operability test program that will be performed on all Class 2 and 3 pumps which are provided with an emergency power source in accordance with Subsection IWP of Code.
This program complies with the requirements'of the Code with the following exceptions.
(1) Pumps in System 2" nominal size or smaller will not be tested.
(2) Pumps will be tested every 92 days instead of 31 days.
- 3. identifies the Class 1, 2 & 3 valves to be tested in accordance with Subsection IWV of the Code. The Davis-Besse Unit 1 procedures are being revised to the extent practical to incorporate the code operability test program. Because of major impact on operating procedures to incorporate the operability requirement on all valves, the procedures will include, to the extent practical, to either partially test or fully test the valves listed in Enclosure 2.
The procedures will be further revised to reflect the balance of the valves requiring testing by the Code by December 31, 197' This valve testing program will meet the Code requirements with the following exceptions.
(1) Class 1 valves 1" nominal size and under will not be inspected.
(2) Class 2 & 3 valves 2" nominal size and under will not be inspected.
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(3) Four valves which were found to be inaccessible and would require plant modification for testing will not be inspected.
(4) Where operation restrictions disallow completed testing of valves during the different modes of operation, the valves will ee partially tested to the extent practical.
Yours very truly, - Pump In-service Inspection Summary - Valve Test Program wr pc 29/5-5c w % >
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Davis-Besse Nuclear Power Station - Unit #1 ENCLOSURE 1 Pump Inservice Inspection Program Stammary Pump No.
Service P&ID Speed Test-Inlet Test-Diff.
Test-Flow Test-Vibra-Test-Lub.
Test-Bearing Test-Remarks able Press.
able
- Press, able able tion able Level able Temp.
able or Press i '
P58-1 ItP Inja:-
M-033 (1)
NA
.X Yes X
Yes X
7es (3)
Yes Level Yes X
Yes tion P58-2 tiP injec-H-033 (1)
NA X
Yes X
Yes X
Yes (3)
Yes Level Yes X
Yes tian P42-1 IP Injec-tt-033 (1)
NA X
Yes X
Yes
- X Yes (3)
Yes I.evel Yes X
Yes
- with min. flow iso, tion (Igi)
P42-2 LP lujec-
- with min. flow iso.
tion (Im)
- t-033 (1)
NA X
Yes X
Yes
- X Yes (3)
Yes level Yes X
Yes P56-1 Contain-ment fbr;a [tf-034 (1)
NA X
Yes X
Yes X
Yes (3)
Yes Level Yes X
Yes j
P56-2 Contain-ment Spray it-034 (1)
NA X
Yes X
Yes 7
Yes (3)
Yes Level Yes X
Yes P3-1 Ser. Water it-041 (1) tiA ore-Yes X
Yes a
Yes(4) (2)(3)
Yes
[ ore-No (2)(3)
Yes t
$ Eel LiEel P3-2 Ser. Water :t-041 (1)
HA Fore Yes X
Yes X
Yes(4) (2)(3)
Yes t'o r e-No (2)(3)
Yes Ita y say I.evel Level P3-3 Ser. Water H-041 (1)
NA Fore-Yes X
Yes X
Yes(4) (2)(3)
Yes Fore-No (2)(3)
Yes Ba y Bay Level Level i-F14-1 Aux. FW l t-O LL B X*
Yes X
Yes X
Yes X
Yes (3)
Yes X
Yes (3)
Yes
- Iurbine driven pumps
/
P14-2 Aux. FW
- t-006B X*
Yes X
Yes X
Yes X
Yes (3)
Yes X
Yes (3)
Yes
- Turbine driven pumps P43-1 Compo-F1-036 (1)
NA X
3ts X
Yes X
Yes (3)
Yes level Yes (3)
Yes nent coolina P43-2 Comgo-tt-036 (1)
NA X
Yes X
Yes X
Yes (3)
Yes Level Yes (3)
Yes Ig.gline P43-3 Compo-H-036 (1)
NA X
Yes X
Yes X
Yes (3)
Yes Level Yes (3)
Yes nent Conting l'E'"d tiotest
- 1. Synchronous or induction motors do not require speed check (lWP 4400).
PA - Not Applicable
- 2. Only upper bearings are accessible.
X - Testing Required
- 3. No instrumentation installed on pumps, use contact type instruments.
- 4. Ultrasonica clamp-on flowmeter will be used, s
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DAVIS-BESSE ENCLOSURE 2 1)
Category A Containment Leak Rate Valves 2 " and larger for Class 2 Valves and 1" and larger for Class 1 Valves, which will be tested to the extent practical.
CC 1407A CV 5007 CV.5077 CV 5089 MU 2A CC 1407B CV 5008 CV 5078 CV 5090 MU 3 CC 1411A CV 5037 CV 5079 DH 11 MU 33 CC 1411B CV 5038 CV 5080 DH 23 RC 229A CC 1567A CV 5065 CV 5081 DH 87 RC 229B CC 1567B CV 5070 CV 5082 DH 88 RC 1719A CS-1530 CV 5071 CV 5083 DH 1517 RC 1719B CS 1531 CV 5072 CV 5084 DH 1518 RC 1773A CV 209 CV 5073 CV 5085 DR 2012A RC 1773B CV 210 CV 5074 CV 5086 DR 2012B CV 5005 CV 5075 CV 5087 DW 6813A CV 5006 CV 5076 CV 5088 DW 6813B 2)
The following are other Valves, Category A, B, C, D, and E, which will be tested to the extent practical.
a.
Pressurizer Code Relief Valves RC 13A, RC 13B b.
Reactor Vent Valves #1, #2, #3, and #4 c.
Core Flood Valves CFIA, CF1B, CF28, CF29, CF30, CF31 d.
ECCS Subsystems Valves DH 14A DH 9B DH 55 HP 56 DH 14B HP 2A DH 64 DH 63 DH 830 HP 2B DH 65 DH 64 DH 831 HP 2C DH 66 DH 84 DH LA DH 7A DH 67 DH 69 DH 1B DH 7B CS 19 DH 127 DH 12 DH 2733 CS 20 HP 2D DH 13A DH 2734 HP 48 DH 13B DH 54 HP 49 DH 9A Containment Spray Valves CS 19, CS 20 e.
f.
Auxiliary Feedwater Valves
.AF 21 MS 730 AF 3871-AF 22 FW 786 AF 3872 MS 106 FW 790 MSICS 38A MS 106A AF 360 MSICS 38B MS 107 AF 388 MS 107A AF 3869 MS 729 AF 3870 i
DAVIS-BESSE Page 2 ENCLOSURE 2 P
g.
Main Steam Valves MS 100, MS 101
'h.
Component Cooling Water Valves CC 1471 CC 123 CC 1338 CC 1467 CC 124 CC 1474 CC 1328 CC 1469 CC 1495 1.
Service Water Valves SW 1356-SW 1399 SW 2929 SW 1357 SW 5421 SW 2930 SW 1367 SW 5422 SW 2931 SW 1424 SW 1382 SW 1358 SW 1429 SW 1383 SW 1366 SW 1434 SW 5 SW 1368 SW 1395 SW 6 cp a/1-2 1
Y a
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