ML17318A293
| ML17318A293 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/06/1979 |
| From: | Dolan J AMERICAN ELECTRIC POWER CO., INC. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| AEP:NRC:00255, AEP:NRC:255, NUDOCS 7910030118 | |
| Download: ML17318A293 (13) | |
Text
AMERICANELECTRIC POWER Service Corporation AEP 2 Broadtttay, Nato York,N. Y. /0004 (212) 440-'9000 JOHN E. DOLAN Vice Chairman Engincning and Construction (2t2J 440-8200 September 6,1979 AEP:NRC:00255 Donald C. Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos. 50-315 and 50-316 License Nos.
Response
to IE Bulletin 79-17 Nr. J.
G. Keppler, Regional Director
" U.S. Nuclear Regulatory Comission Office of Inspection and Enforcem nt Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Hr. Keppler:
This letter responds to your letter dated July 26, 1979 which trans-mitted to us IE Bulletin 79-17 entitled "Pipe Cracks in Stagnant Borated Water Systems at PWR Plants."
As required by this Bulletin, we have
'onducted a review of safety-related stainless steel piping systems and have identified those portions of systems which contain stagnant borated water and have tabulated these portions of systems in Attachment 1.
The list presented in our response dated April 15, 1977 to IE Circular 76-06 has been expanded to include minor branch connections and bypass loops which are appendages to these safety-related systems.
Res onse to Item 1
a of IE'ulletin No. 79-17 The non-destructive examination (NDE) plan for the D. C. Cook Nuclear Plant Units 1 and 2 is in accordance with the ASME Code Section XI which requires NDE for only the Class 1 portions of the identified piping lines.
Preservice NDE was performed in October 1974 and December 1977 for Units 1
and 2, respectively.
Scheduled inservice inspections for Unit 1 were per-formed in January 1977 and April 1979.
The first inservice inspection (ISI) for Unit 2 is scheduled for November 1979.
Tables 1
and 2 of Attachment 2
show the extent of the preservice and inservice NDE inspections for each Unit.
Mr. J.
G. Keppler, Di) tor :NRC:00255 NDE procedures for ultrasonic and visual examinations used in the 1977 and 1979 ISI's were issued by Southwest Research Institute (SWRI).
The 1977 ISI procedures met the requirements of the 1971 Edition of ASME Code Section XI with Addenda through Winter 1971, and the 1979 ISI procedures were written in accordance with the 1974 Edition of the ASME Code Section XI with Addenda through Summer 1975.
The information requested concerning the NDE procedures, procedure qualifications and acceptance criteria is
'given in Attachment 3 of this response.
No indications were observed during exami nation of pipi ng systems containing stagnant borated water which resulted from other than geometric configurations of the weld joints.
In response to IE Circular 76-06, hydrostatic leak tests were conducted in Unit 1 in September 1977 on those piping lines identified in note 1 of.
These tests were conducted in accordance with the 1974 Edition of ASME Code Section XI with Addenda through Summer 1975.
The results of these tests are acceptable.
These tests have been scheduled to be performed on Unit 2 as part of our ISI program.
Res onse to Item 1
b of IE Bulletin No. 79-17 The portions of piping systems identified in Attachment 1 are part of or are appendages of systems in which water chemistry is monitored and controls are maintained.
The results of sampling these systems have been acceptable.
Attachment 4 to this letter provides a summary of typical water chemistry data taken in the Boric Acid Storage Tanks (BAST), the Boron Injection Tanks (BIT), the Residual Heat Rermval (RHR) systems and the Demineralized Water System.
Res onse to Item 1
c of IE Bulletin No. 79-17 The preservice NDE included visual, surface and volumetric examinations of ASME Code Class 1 components in accordance with the 1971 Edition of ASME Code Section XI with Addenda through Winter 1971.
The acceptance criteria were per Article IS-311 of that Code Edition.
Res onse to Item 1
d of IE Bulletin No. 79-17 A review of plant records for both Units 1
and 2 shows no evidence of work done to repair cracking in the piping lines identified in Attachment l.
Very truly yours,
. JED: clb attachments cc:
(attached) ohn,E.
Dolan lce Chairman
Mr. J.
G. Keppler, Dir tor A
- NRC:00255 cc:
Norman C. Moseley -
NRC R.
C. Callen G. Charnoff D. V. Shaller - Bridgman R. S. Hunter R.
W. Jurgensen
DONALD C.
COOK NUCLEAR PLANT UNITS 1
& 2
Response
to IE Bul etin 79-17 AEP:
irRC:
00255 A
chment 1
The port".ons of safety-related piping systems in the Cook 'lucr e."-ir Plant containing Bor-c Acid solution vhich come under the criteria of not beinG frequently f'ushed or con-
~ taininG non-flovir>> liauids are:
1)
Accumulator to Reactor Coolant System Cola Leg.
2)
Boron Injection "ank to Reactor Coolan+
Sy tem.
3)
Refue'ing Uater StoraGe Tank to CVCS.
4)
RHR Valves ICH 305 5 306 to Pumps.
5)
RHR Pump Suet'on to Contain..ent Sp ay Pump Suction.
6)
Spray Additive Tank to Containment Spray 7)
Crosstie Safety Injection to CVCS.
8)
9)
. Valves Il!0 330 Zc 331.
10)
Safety Injection to Reactor Cool,. t Syste-... Cold Leg.
ll)
Safetv Injection to Reactor Coo"ant Sys"em Hot Leg.
12)
RHR to Reactor Coolant System Cold Leg.
13)
RHR to Reactor Coolant Sy
+em Hot Leg.
14)
Blender llakeup to Hefucling 3'ater Storage Tank (R"'S ).
1))
Refuel ng >'ater Storage Tank to Purificat'on Pump.
1b)
Pur'ficat'on Filter to ZJST.
1'P)
ECCS Check Valve Leakage Testing L"'nes.
18)
RHR return to R'i/ST.
19)
20)
Charging Pump Discharge to Boron Injection Tank.
21)
RHR Hot Leg return.
22)
RHR Cold Leg Cooldown line.
23)
HHH ice:.t Zxcbger (Psst 5 'e'cst) Outlet Oclc Leg Cooldown line.
24)
HH11 Pump Discharge Crosstie.
25)
Boron Injection Tank bypass.
26)
Test Line to Spray Additive Tank.
27)
HiO< Heat Exchanger Outlet Cro"stie.
28)
Alternate 3CP Seal.injection.
29)
BCP Seal Filter bypa s.
Notes:
1)
Piping systems 1 through 19 were hyerostatically leak-tested in Unit 1 during September 1977.
2)
Modifications were made to sy tern lb in Unit 2.
This system is no longer st,.cnant.
DONALD C.
COOK NUCLEAR PLANT UNITS 1
& 2
Response
to IE Bulletin 79-17 AEP:
NRC:
00255 Attachment 2
TABLE 1 A
LD AEP:
NRC:
002/5 I'N AN S
G ITEN+
OAE W
DESCRIPTION ECCS-Xe (LHSI) to Hot Leg SIZE 8>>D.
.812>>T 6>>D NO ~
VT T
6 90 NO OF WELD EXAMS ISI 1977 VT T
0 7
NO ~
~ 812 0
0 ECCS SIS (Acc~o 10>>Do 1 000 T In].) Cold Legs 10 ECCS-RHR (LHSI)
Cold Leg 6>>D
,718>>T B.I.T. to RCS l-l/2>>D.
Socket Welds 102 (VT/PT) 9(VT/PT) 8 (PT) 21 RHR Hot Leg Return 14 D. 1.406 T
+REFERENCE TO ITEMS " ATTACHMENT 1
AEPs NRC!
00255
'TABLE C OK -
PIPING CIRCUMFER TIAL WELD LIST -(CONTINUED)
NOTES'.
Listing Includes Circ. Welds Only.
2.
All Areas Listed Are Within R.C.P.B., Safety Class 1, Unit 1.
3.
Areas Listed Are Applicable To Items 1.A and 1.C of I.E. Bulletn 79-17.
4.
PSI Examinations In Accordance With ASME XI 71W71.
5.
No Reportable UT Or PT Indications.
VT Revealed ARC Strikes and Gouges Which Were Repaired/Resolved.
TABLE 2 AEP:
NRC:
00255 PPNG NGS N
BOAE WA R
FERE L WELDS N POR 0 '
S EYS DESCRIPTION S ZE NO.
OF MELD EXAMS PSI
-0 VT T
ECCS-RHR (LHSI) to Hot Leg 22 69 12 RHR to RCS Cold Leg 8" D..812" T.
ECCS-SIS (Accum. In).)
10" D. 1.000" T.
to Cold Legs 91 10 ECCS-RHR (LHSI) to Cold Legs 6)'
718" T 25 B.I.T. to RCS 1-1/2"D. Socket Welds 123(VT/PT)
RHR Hot Leg Return 14-" D. 1.406 21 NOTES:
1.
Listing Includes Circ. Melds Only.
2.
All Areas Listed Are within R.C.P.B., Safety Class 1, Unit.2.
3 ~
Areas Listed Are Applicable To Items 1.A and 1.C of I. E.Bulletin 79-17.
PSI Examinations In Accordance With ASME XI-71M71.
5.
No Reportable UT Or PT Indications.
VT Revealed Arc Strikes And Gouges Which Were Repaired/Resolved.
REFERENCE TO ITEMS - ATTACIKENT 50 ~ 1
Donald C.
Cook Nuclear riant
'Unit Nos.
1 and 2
Response
to IE Bulletin 79-17 AEP:NRC:00255 Attachment 3
DESCRIPTION 8
UALIFICATION OF NDE PROCEDURES Ultrasonic (UT) examinations were performed in accordance with SWRI Procedure No. 600-3, "Manual Ultrasonic Examination of Pressure Piping Welds."
Revision No.
25 of this procedure was used in 1977 and Revision 52 was used in 1979.
In both cases the examinations consisted of
-attenuation and thickness measurements upstream and downstream of the weld.
Longitudinal wave scans for laminations were performed prior to shear wave scans over the volume to be examined by shear wave.
Both 45 and 60 degree shear waves
(+ 2 degrees) were directed from both sides, perpendicularly to the weld, to include a volume of one wall thickness of base metal.
Where examination from one side of the weld was not feasible, a longi-tudinal wave examination was performed on the volume not covered by shear wave.
The shear wave scan was made at a 45 degree angle clockwise and counter-clockwise from the weld surface in all cases.
The shear wave search unit utilized a 1/2" round or 1/2" x 1/2", 1.5 MHz transducer.
The scanning technique required a
10 percent minimum coverage overlap at a six inches per second maximum rate.
Scanning was performed at two times the calibrated reference level sensitivity.
All UT indications of an amplitude reater than or equal to 50/ of the distance amplitude correction curve DAC) were recorded.
Any indications, irrespecti ve of amplitude, suspected by the examiner to have originated from other than geometric reflectors were recorded and investigated.
All indications greater than or equal to 1005 of DAC and those suspected by the examiner to have originated from other than geometric reflectors were investigated to the extent necessary to determine the reflector's
- shape, size, identity and location.
The acceptance criteria specified in all NDE procedures are in accordance with Article IS-311 (for the 1977 ISI) or Article IWA-3000 (for the 1979 ISI).
The SWRI NDE procedures used were qualified in accordance with SWRI Operating Procedure No. IX-FE-107.
Procedure 600-3, Revision 25,.was qualified by code reference (1971 Edition of ASME Code Section XI., III, and V with Addenda through Winter 1971); by calibration, and by detection of confirmed flaws.
Procedure 600-3 Revision 52 was qualified by code reference (1974 Edition of the ASME Code Section XI, III, and V with Addenda through Surfer 1975),
by calibration, and by similarity to Revision 25.
DONALD C.
COOK N
EAR PLANT UNITS 1 2
Response
to IE Bulletin 79-17 P:
NRC:
00255 Attachment 4
TYPICAL ANALYTICAL DATA "N" BAST "M" BAST "S" BAST BORON 2-2175 21425 21962 21630 21470 21443 21896 21507 20758 21077 21539 C1
<1.0 PPM
<1.0 PPM 21235 21062 20828 21026 20630 21726 21387.
21314 21290 21178 0
<1.0 PPM BORON 20776 20806 20934 20717 20618 20416 21428 20586 20458 20097 20684 C1
<1.0 PPM
<1.0 PPM UNIT 1 BIT BORON C1 BORON C1 UNIT 2 BIT 21709
<1.0 PPM 21536 21405 21264 21064 21215 21199 20931 21013 21199
< 1.0 Ppt1 21254 DEMINERALIZED MATER 20691 20754 20762 20667 20959 20672 21218 21914 21958 21105 21070
<1.0 PPM
<1.0 PPt4 6.60 7.80 7.20 7.70 7.80 7.95 7.80 6.95
'.20 6.85 7.39 C't
<.05 PPM
<0.05 PPM
~0~)b) 15 ppb 10 10 10 10 10 10 10 10 10
- 10. 5 Boron not run
RHR UNIT 1 AEP':
NRC:
00255
'tachment 4
RHR U
2 1
~ pH
- 5. 80 5.. 60 5.80 5.57 5.6
.5.85 5.60 5.8 5.6 5.6 3.68
<Q.
<0.
C1 05 PPH 05 Pr r4 F
<0 2157 2149 2144 2115 2154 2152 2152 2115 05 PPt1 2142 2143
<0.05 PPi~f 2151 pH 6.6 6.6 6.6 6.55 6.70 6.78 6.50 6.80 6.50 6.68 6.64
.05 PPH
<0. 05 PPM
<0. 05 PPM
<0.05 PPH
<0 Boron 978 980 981 978 968 977 966 981 964 952re
(