ML20086T487
| ML20086T487 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/01/1984 |
| From: | GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20086T484 | List: |
| References | |
| PROC-840301, TAC-54588, NUDOCS 8403060393 | |
| Download: ML20086T487 (15) | |
Text
'.
f,. .
March 1, 1984 i
f INSERVICE INSPECTION PLAN For ASME Class 1, 2 and 3 Components Cooper Nuclear Station Unit 1 .
Nebraska Public Power District Prepared By General Electric Company ,
Domestic Apparatus And Engineering Services Operation f.y hkO g
e
,e INSERVICE INSPECTION PLAN TABLE OF CONTENTS DESCRIPTION PAGE NO.
1.0 BASIS FOR THE INSERVICE INSPECTION PROGRAM 3 4
2.0 THE SECOND TEN YEAR INSPECTION INTERVAL 3 3.0 -APPLICABLE ASME CODE 3 4.0 INSERVICE INSPECTION PLAN 3 5.0 INSERVICE INSPECTION PROGRAM 4 6.0' EXTENT OF EXAMINATIONS 4 7.0 EXAMINATION BOUNDARIES 5
~
8.0 AUGMENTED INSERVICE INSPECTIONS 6 9.0 RELIEF REQUESTS 7 l .
2 e
INSERVICE INSPECTION PLAN 1.0 Basis For The Inservice Inspection Program The base document from which the ISI plan, schedule, and program are developed is 10CFR50.55a(g). Burns and Roe, the Architect Engineer for Cooper Nuclear Station during construction were NPPD's agent in determin the ASME Code classificationslof our plant components. NRC Reg. Guide 1.26 was not yet published; hence, it was not used during Burns and Roe's classification.
NPPD has not nor are there plans to reclassify all the plant components in accordance with the newer regulations and guides.
2.0 The Second Ten Year Inspection Interval 2.1 The commercial operation date for Cooper Nuclear Station is July 1 1974. The end of the first interval is June 30, 1984, and the Second Ten Year Interval is July 1, 1984 to June 30, 1994.
2.2 The three 40 month inspection periods during'the second interval are as follows:
1st period: From July 1, 1984 to October 31, 1987.
2nd period:
From November 1, 1987 to February 28, 1991.
3rd period: From March 1, 1991 to June 30, 1994.
o 3.0 Applicable ASME Code The Inservice Inspection of ASME Class 1, 2 and 3 Components are performed in accordance with Section XI of the ASME Boiler and Pressure oe Ves g
lief from examinations and testings determined to be im granted by the NRC pursuant to 10 CFR Part' 50, Section 50.55a (g) (6) (i).
4.0 Inservice Inspection Plan 4.1 The Inservice Inspection (ISI) Plan is a general document which is provided to the regulatory authorities.
4.2 The ISI Plan Provides:
4.2.1 Extent of examination 4.2.2 Examination boundaries 4.2.3 Relief Requests 4.2.4 Basis from which the detailed ISI Program is established.
3
w 5.0 Insarvico Inspection Progran 5.1 The Incervice Inspection (ISI) Program is a detailed living document which is available to the regulatory authorities for audit.
5.2 The.ISI Program provides:
5.2.1 ASME Section XI examination catagory and item listing 5.2.2 Specific examination identification and location 5.2.3 Weld joint configurations 5.2.4 Nondestructive examination procedures 5.2.5 Ultrasonic calibration standards list 5.2.6 Applicable list of Isometric drawings 5.2.7 Augmented Inservice Inspections 5.2.8 Relief Requests 5.2.9 Status of completed inspections 5.2.10 Summary of previous Inservice Inspections 5.3 The Scheduling of Inservice Inspections is in accordance with ASME Section XI. The mechanism for specific component scheduling is contained in Cooper Nuclear Station procedures. This form of scheduling provides for optimization of component inspection during normal ALARA.
refueling and maintenance activities and maintains exposure 5.4 All records and reports are prepared in accordance with ASME Section XI IWA-6000. -
6.0 Extent of Examinations 6.1 All components are examined in accordance with ASME Section XI, Subsections IWA, IWB, IWC, IWD, and IWF.
6.1.1 The extent of examinations for Code Class 1 and 2 pipe welds are determined by the requirements of Table IWB-2500 and IWB-2600, Category B-J for Class 1 and paragraph IWC-2411 Category C-F and C-G for Class 2 in the 1974 Edition through the Summer 1975 Addenda of ASME Section XI, c
4
6.1.2 ASME Section XI (Winter 1981), Subsection IWE, " Requirements for Class MC Components of Light-Water Cooled Power Plants" was added to Section XI since Summer 1975. However, 10CFR50.55a presently only incorporates those portions of Section XI that address the ISI requirements for Class 1, 2 and 3 components and their supports. The regulation does not currently address the ISI of containments. Hence, ISI of MC Components and their supports are not included in the ISI Plan and Program'*.
6.2 All Class 1, 2 and 3 piping components have been reviewed against the respective ASME Section XI IWB-1220, IWC-1220 and IWD-1220 exemption criteria.
6.3 Appropriate Code Class 2 pipe welds in Residual Heat Removal Systems, Emergency Core' Cooling System and Containment Heat Removal Systems shall be examined.
6.4 All Class 3 systems and exempt Class 1 and 2 components require only a visual examination during pressure tests. The piping and
- instrumentation drawings are used during the visual exams to aid in the location and position of any components which have reportable discrepancies during the pressure tests.
6.5 Determination of ASME Section XI Code Categories for Class 1, 2 and 3 components.
6.5.1 All Class 1, 2 and 3 components are categorized in accordance with ASME Section XI Table IWB-2500-1, Table IWC-2500-1 and Table IWD-2500-1 respectively.
7.0 Examination Boundaries 7.1 Examination boundaries are those ASME Class 1, 2 and 3 fabricated and
'+ installed components, their attachments and supports.
7.2 ASME Class 1, 2 and 3 boundaries are identified on Color Coded P& ids and are located at the Cooper Nuclear Station.
l l
7.3 The following Systems or portions of Systems are included in the ISI examination boundaries.
7.3.1 - Atmospheric Containment Atmosphere Depressurization i 7.3.2 - Circulating Screenwash and Service Water l 7.3.3 - Condensate l 7.3.4 - Control Rod Drive Hydraulic
! 7.3.6 - Core Spray 7.3.7 - Drywell Heating and Ventilating 7.3.7 - Feedwater 7.3.8 - Fuel Pool Cooling and Clean-up i 7.3.9 - Heating and ventilating standby Gas Treatment ano Off Gas Filters 7.3.10 - High Conductivity Floor Drains 7.3.11 - High Pressure Coolant Injection
- From the Federal Register / Volume 48, No. 26; 10CFR Part 50 Dated Monday, February 7, 1983, Supplementary Information.
5
7.3.12 - Jet Pump Instrumentation 7.3.13 -- Main Steam 7.3.14 - Post Accident Sampling 7.3.15 - Primary Containment Cooling and Nitrogen Inerting 7.3.16 - Reactor Building and Drywell Equipment Drain 7.3.17 - Reactor Core Isolation Cooling 7.3.18 - Reactor Building Floor and Roof Drains 7.3.19 - Reactor Recirculation 7.3.20 - Reactor Water Clean-up 7.3.21 Residual Heat Removal 7.3.22 - Service Air and Control Air-8.0 Augmented Inservice Inspections I Augumented Inservice Inspections (AISI) are not ASME Section XI Code Requirements but are 1) additional examination areas, or 2) increased inspection frequency or combinations of both which are requested by the Nuclear Regulatory Commission.
When examination components fall into the scheduled testing of both ISI and AISI, then credit for both requirements are taken (no double. testing).
There are presently 6 types of Augumented Inservice Inspections required at Cooper Nuclear Station:
TYPE DESCRIPTION 1 All those ASME Category B-F and B-J welds which are designated " pipe whip" welds shall be inspected each ten year interval (reference CNS Technical Specifications Table 4.6.4). Type 1 AISI is an increase in frequency of exams for selected ASME Category B-J welds to once every ten*
year interval.
2 All ring girder, bolting and ring girder anchor bolting is to be .
volumetrically inspected each ten year interval. The Anchor Bolting ad jacent to the Inboard MSIV is -to be visually inspected;each ten year .
interval. (Reference NRC DRO Bu11etin-#74-3).
(
l 3 Welds susceptible to Intergranular Stress Corrosion Cracking that are to be inspected per the Optimized ISI' Program
- required by NUREG-0313.
I 4 Ultrasonic examination of the feedwater nozzle safe ends, bores, and inside blend radii, liquid penetrant examination of the feedwater nozzles, and visual inspection of the feedwater spargers as required per l
Table 2 and Section 4.3.2.4 of NUREG-0619.
5 Ultrasonic examinations, utilizing GE procedure TP508.0654 Rev. D or equivalent, are conducted to assess the integrity of the jet pump hold-down beams at the mid length ligament areas bounding the beam bolt.
These examintions shall be performed each refueling outage. (Reference IE Bulletin No. 80-07).
- The Optimized ISI Program is now under' development. The welds will be incorporat-ed in the ISI Program af ter completion of the Optimized ISI Program.
6
7_ _
TYPE DESCRIPTION 6 Visual inspection of the Core Spray Spargers and the Core Spray Piping inside the RPV shall be inspected each refueling outage. (Reference IE Bulletin No. 80-13).
9.0 Relief Requests 9.1 When an ASME Code Class 1, 2 or 3 component is determined to be impractical to inspect in accordance with ASME Section XI IWA-2000, IWB-2000, IWC-2000, IWD-2000 or IWF-2000, a specific written relief request from the ASME Code is submitted to the NRC in at.cordance with Section 3.0 (above). Each written relief request contains the following information as a minimum:
9.1.1 Identification of component (s) for which relief is requested 9.1.2 ASME Section III Code Class 9.1.3 The specific ASME Code requirement. that has been determined to be impractical 9.1.4 Cooper' Nuclear Station relief justification (s) information for requesting relief.
9.1.5 Specific alternative inspection (s) in lieu of ASME Code Section XI requirement (s). ,
9.2 The following is a list of Relief Requests.
Relief Request No. Description 1 ASME Category B-J, Inaccessible Nelds, primary containment 2 ASME Category C-F, Inaccessil'u welds, encassed in
! concrete 3 ASME Category B-D, RPV Top Head Nozzle inner radii l 4 ASME Category B-L-2, Internal Surfaces of Pumps l
l 5 ASME Category B-M-2 Internal Surfaces of Valves l
l l
l 7
r
- d k -
- n at oec il t
ua d e cf nt 2 E eooscy p
V s e sf I
T nce o f AT i nb e o NS 7 e ht .
RE 0 l dl t s0 O ET ail uvigt 0 e0 T
L s ewno5 n A i ir -
I o vrerdB ogu yW i
s Af adhI e i s v a e r R e - -
h y
d mr h c
t l au F t l eexs t E ,nb r we ce I nemu gmes grerS rik L
E i nss noht R si eaarsp eif t i ee n e R 6 d t pi eeuS O 0 nn pl l (
F sooe t c i n gi b v b yo
)
S i t ons .d I ya isnrs e S orrsneoodh
~
A t at eici oc G R mevact eh a N einat aact t I ureeennaet P D ppl riif ma I
P D
N 1 A T N 0
" S O I N 0 T I I E 5
' N T M 2d
" E N
A T
NTE OSR 5
- nc B ai
"' O P
M S
R I EI TTU C Q 0 W I et c e r
" O A E E E am
' C E S R Lf u L B rl
' R C A uo O U TSV F W
_ S R T E S P
_ E O -
U O T n
_ Q C DN e
- E EE rt TN R
et PO 4 f u
_ F MP 0 mB E EM u s I XO cl d L EC ral E ii e R Ct w YM RER OTE 3 l
CIB l
_ E M 0 J .
TDU - 9 ANN BB CA C
I R S S
T A 2 C L C
0 l E
L E RT ONE
0 A YO WS SC FM R
E N T FS E EE 0 1 I U G LQ 0 0 EE I RR R I,
1
- l
. 8 ,:, -
=
! -i=,=
I a 25
~=
~
t* I :Er gs*5a I ti
~ 5 s .
o - s _
' ItI=g.
> N r i i '
=== ss ' -
r "
9 F %d '
f n .
p 9 p
$ j p f p -
G
- f G 9
_1 1
- ir. .*. f e. ;f,! $
gw # 1 M Y', .M. g i
=.a.~. -
,. : p p aa. -
, . . i :% -
1 j .[..ll $ ) 9 W Ni i
a of '{ s m ' '
i i i
A, l' '
.[ ..
i
. .. ,3..
, v:.
1
. g. : < - : .
p 9 ,: .<* .r--
~q~ ;;;.a;=...s y . .
- ? * * =c. = -
h h
+
s
+_ ;$ .
s_ _f .
~
I g u -
3- .
s.
i ,
INSERVICE INSPECTION FaE. 1 of 1 .,
GENER AL @ ELECTRIC RELIEF REQUESTS FOR COMPONENTS AND FIFING
- Revision 0
_ COOPER NUCLEAR STATION CATEGORY SECTION II RELIEF SYSTEM OR CLASS AND ITEN EXEMPTED TEST RASIS FOR RELIEF ALTERNATIVE COMPONENT NUMBER COMPONENT REQUIREMNT TEST REQUEST 00 01 02 03 04 05 06 07 RI-02 IIP 2 C-F Pressure TABLE IWC-2500-1 The underground locat- A visual examinatir n LP C5.Il Retaining Surface ion of these welds consisting of a RI C5.12 Welds in makes a surface exam- presure leakage tes t Piping. ination impractical. thct determines the-Section IWC-1230 of rate of pressure ASME Section XI re- loss will be con-cognizes the impracti- ducted during the cality of examination system pressure of inaccessible com- test requirement of ponents encased in IWC-5000 concrete. We believe it's intent may also be applied to inac-cess ible components that are under ground.
Imposing the Code requirements would r'e su l t in hardships or unusual difficulty without a compensating increase in quality and safety because the structural integrity has fabrication exam-ination and by perfor-mance of the alterna-tive test.
I
IEdERVICE INSFECTION Fase 1 or 1 .
GENER AL $ ELECTRIC .
RELIEF REQUESTS FOR COMPOdEKIS AND FIFING Revision 0 C00FER NUCLEAR STAT 1 1 CATEGORY SECTION II RELIEF SYSTEM OR CLASS AND ITEM EEEMPTED TEST RASIS FOR RELIEF ALTERNATIVE COMPONErr NUMBER COMPONErf REQUIREME W TEST REQUEST 00 01 02 03 04 05 06 07 RI-03 N7-IIeal 1 B-D N7 NIR ._ TABLE IWB-2500-1 Request surface exam- Surface Examination Spray Nozz e B3.100 Volumetric exam- ination of the nozzle Inner Radit.s N8 NIR nation of the inner radius.
NB-Vent nozzle inner Nozzle Inner N18 NIR radius is The RPV Closure Head Radius required. is removed during re-N18-Spare fueling activities Nozzle Inni r allowing access to the Radius RPV Closure llead NIR.
A surface examination is more sensitive in detecting surface de-fects at the NIR.
l i
" " "*" " ~
Fage i or 2 G E N E R AL 4ll> E LECTRIC RELIEF REQUESTS FOR COMPONENIS AND FIPING Revision 0 COOPER NUCLEAR STATION CATEGORY SECTION II CLASS AND ITEN EXEMPTED TEST RASIS FOR RELIEF ALTERNATIVE RELIEF SYSTEN OR NUMBER COMPONENT REQUIREMENT TEST REQUEST COMPONENT 02 03 04 05 06 07 00 01 RI-04 Recirculat- 1 B-L-2 Internal TABLE IWB-2500-1 The recirculation A visual inspectior ,
ion pumps 1 B12.20 surface of Visual examina- pump casing material to the extent pump casing tion of I of 2 is a cast stainless practical, will be pumps each steel. This material completed only wher 10-year interval type has performed the pump is very'well in nuclear diseasembled for service and has demon- maintenance.
strated substantial resistance to such chemical processes as
- ' pitting corrosion and stresa corrosion crack-
'ing which would de-crease the structural integrity of the pump.
To do the required visual inspection of this pump's internal surfaces, large amounts of radiation exposure and time would be required.
This was demonstrated at a similar nuclear station, where an expenditure of approximately 1000 man-hours and 50 man-rem was required to complete the visual inspection of similar designed pump.
f Page 2 of 2 ,
G E N E R AL 4ll> E LECTRIC RELIEF REQUESTS FOR COMPONENTS AND PIPING Revision 0 COOPER NUCLEAR STATION CATEGORY SECTION II RELIEF SYSTEM OR CLASS AND ITEM EXEMPTED TEST RASIS FOR RELIEF ALTERNATIVR REQUEST COMPONENT NUMERR COMPONEtrF REQUIREM NT TEST 00 01 02 03 04 05 06 07 RI-04 The large expenditure (cont'd) of man-rem and man-hours to complete the visual inspection of a perfectly good pump solely for,the pur-pose of inspection is impractical and not
~
commensurate to the in-creased safety achieved by the inspection.
Cooper Nuclear Station believes that adequate safety margins are in-herent in the basic pump design and that the health and safety of the public will not be adversely affected by not performing the visual examination of the pump casing internal surfaces solely for the purpose of inspection. If, however, a pump requires disassembly for maintenance, then a visual inspection, to the extent practical, will be performed.
GENER AL $ ELECTRIC rag. 1 or 2 .
RELIEF REQUESTS FOR COMPONElfrS AND PIFING Revision O COOPER NUCLEAR STATION CATEGORY SECTION II RELIEF SYSTEM OR CLASS AND ITEM EXEMPTED TEST RASIS FOR RELIEF ALTERNATIVE REQUEST COMPONENT NUMBER CONFONENT REQUIREMENT TEST 00 01 02 03 04 05 06 07 RI-05 All Class 1 B-M-2 Internal TABLE IWB-2500-1 The requirement to A visual inspectiot valves ex- B12.40 surface of Visual examina- disassemble an operable of a valve (1 per ceeding 4 valve bodies tion of I valve valve for the sole pur- group per interval) inches in each group pose of performing a internal surface wi ll normal of valves (as visual examination of be performed when t be pipe size specified in the internal pressure valve is disassembi ed
_ca t egory B-M- 2 ) boundary is impractical for maintenance.
each 10-year and not commensurate to interval. the increased safety achieved by the in-spection and has only a very small potential of 5
increasing plant safety margins with a very disproportionate impact on expenditures of plant maapower and radiation exposure.
Performing these visual examinations under such adverse conditions as high dose rate (10R/Hr) and poor as-cast surface condition, pro-vides little additionalinformation as to the valve casing ir enrity.
l
E 2 V I
T f AT o NS 7 RE 0 ET 2 0 T L
n A i
o s
e i t v a e l a r R h t ne t a .
o sl ot ct yod ef n n oeyet l no ,
b s al i a i at neh or F sh a t u sh e t t erivl h a aqeatfl c st otl b t , c .
E f e al egnnf cam I
L ol sn . t erb neisSd a d sif noi eve ,nid ot e E eii n a en wfii yp s ei c m R c ad eor sh ad amt yl s as ct ar nt oniat nt nc rcd en ancro
,s a e pf R 6 asb et eai naiyoeol i l l f pb o rinp r O 0 m l al h gng F rd el cct riihb ers sf ed est e onveiu a st us ene ov t nnp S f al cl N s mt el p r pi vs es nie I r axp e nd a e l eewei t e S enveprvye eevtl acs oral xb A po aeet r ehhd oavaohi mae f p u u l G B b t n pi eev t anu s err ,qrs el N ers eR ol f hl e I h aaeW oeanahf e yi h uuf eoihi P T ccbBCb sivt obb vt s pI rf vt w I
P D
N A
N T
" S O I N T I I E N T M E A NTE N T OSR 5 O S I EI 0 P TTU M R C Q
" O A E E C E S R ,
L R C O U F N
" S R
' T E
" S E
U P
O O T Q C DN E EE _
R TN PO 4 F MP 0 E EM e I XO L EC E
R YM RER OTE CIB 3 E M 0 TDU ANN CA C
I R S S
T A 2 C L C
0 E
L E
RT ON
1 0
A YO SC R
E )
N T d FS '
E EE 5 t IU 0 G LQ 0 0 n
- o EE I c RR R(