ML19249F046
| ML19249F046 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 08/24/1979 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7910030870 | |
| Download: ML19249F046 (14) | |
Text
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C CONNECTICUT YANKEE AT O M IC POWER COMPANY k
1 BERLIN. CONNECTICUT P. O. BOX 270 H A RTFORD. CONN ECTICUT 06101 Tatapuout 203-666-6911 August 24, 1979 Docket No. 50-213 Mr. Boyce H. Grier, Director Region I Office of Inspection and Enforceme.nt U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Reference:
(1)
B. H. Grier letter to W. G. Counsil dated July 26, 1979, forwarding I&E Bulletin #79-17.
Gentlemen:
Haddam Neck Plant Pipe Cracks in Stagnant Borated Water Systems at PWR Plants I&E Bulletin No. 79-17, Reference (1), requested that Connecticut Yankea Atomic Power Company (CYAPCO) conduct a review of safety-related stainless steel piping systems to identify systems and portions of systems which contain stagnant oxygenated borated water.
In addition, the NRC Staff requested that CYAPC0 provide specific information regarding these systems within 30 days of the date of the Bulletin. Accordingly, CYAPCO hereby provides the attached responses to Items 1(a) - 1(d) of Reference (1).
CYAPCO Ins performed a review of safety-related stainless steel piping to deter-mine which systems contain stagnant oxygenated borated water. CYAPC0 has defined any piping not flushed at least once per month as stagnant. This definition is based on the following:
(1) no cracks were found in the high-pressure injection lines at Three Mile Island, Unit No.1 (TMI-1) which were occasionally flushed; (2) this definition allows a large enough sample of welds to produce a statistically meaningful test; (3) the piping to be tested should contain the worst case welds as the fluid is motionless for the longest period of time.
In addition, examinations will be limited to Type 304 stainless steel piping based upon the fact that cracks detected at TMI-l were in Type 304 piping systems and testing performed under Contract by the Electric Power Research Institute (EPRI)
(GE Report NEDO-21000) has shown Type 304 stainless steel to be far more susceptible to intergranular stress corrosion cracking (IGSCC) than other types such as Types 316, 316L, and 304L.
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6 7910080c}7C
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. Based on the above, the following systems and portions of systems are considered to contain stagnant oxygenated borated water:
(1) Residual liest Removal System - portions which are not recirculated.
(2) Low Pressure Safety Injection Systems - portions downstream of LPSI pumps.
(3) Chemical and Volume Control System - dead legs only.
CYAPC0 wishes to note that the examination to verify system integrity outlined in Item 2(a) of the Bulletin has been defined as a visual examination at service pressure of normally accessible welds. Guidance for this visual examination of welds will be drawn from IWA-5240 which states that insulation will be removed only if evidence of leakage is found at a low point or under a pipe. This defini-tion was chosen as it more appropriately addresses the intent of the inspection.
CYAPCO trusts that this information is responsive to NRC Staff's requests and concerns.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY
/ -
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, g ), f W. G. Counsil Vice President Attachment 108i i"7
DOCKET NO. 50-213 ATTACINENT HADDAM NECK PLANT 1&E BULLETIN No. 79-17 RESPONSE TO ITEMS 1(a) - 1(d) nn4 i~'O L,'l l
U AUGUST, 1979
,r i
Question 1(a)
Provide the extent and dates of the hydrotests, visual and volumetric examina-tions performed per 10CFR50.55a(g) (Re:
IE Circular 76-06 enclosed) of identified systems.
Include a description of the non-destructive examination procedures, procedure qualifications and acceptance criteria, the sampling plan, results of the examinations, and any related corrective actions taken.
Response
No inservice inspection visual, volumetric examinations, or hydrotests have been performed on these systems. As described in the D. C. Switzer letter to A. Schwencer dated June 29, 1977, these piping systems are exempt from non-destructive examinations provided that the chemistry of the contained fluid is periodically sampled. This exemption is based on Subsection IWC-1220c of Section XI.
The first ten-year hydrotest of these systems will be conducted during the 1980 refueling outage. Monthly ISI pump testing does serve to provide flow through portions of these systems at system pressure on a regular basis, and no abnormal leakages have been detected.
Question 1(b)
Provide a description of water chemistry controls, summary of chemistry data, any design changes and/or actions taken, such as periodic flushing of recircula-tion procedures to maintain required water chemistry with respect to pH, B, CL,
F,0- 2
Response
The above described chemistry program is performed in accordance with the attached procedure 5.4-26, " Inservice Inspection Chemical Sampling Program".
This procedure is presently under revision to incorporate additional elements and specific restrictions on the concentrations which are acceptable. The elements that will be analyzed and the acceptable concentrations are provided below:
pH.
. will vary with boron concentration.
Conductivity.
. will vary with boron and other constituents.
Fe.
. < 1. 0 mg/ L Na
. < 0.1 mg/ t Cr.
. < l. 0 mg/ l Mg.
. < 0.05 mg/ L p n *I 1"Q
.a i
. Ca.
. < 0.05 mg/ t Al.
. < 0.05 mg/ t Li.
. < 0. 7-2. 2 mg/ E Ni.
. < 1. 0 mg/ t Cl...
.<.15 mg/t Suspended solids.
. < 1. 0 mg/ E A sample of the chemistry data taken during December,1978 is also attached.
Also, the monthly ISI pump tests mentioned above serve as a periodic flushing of certain portions of these systems.
Question 1(c)
Describe the preservice NDE performed on the weld joints of identified systems.
The description is to include the applicable ASME Code sectione and supplements (addenda) that were followed, and the acceptance criterion.
Response
The identified systems, which include portions of Low Pressure Safety Injection, Residual Heat Removal and Chemical Volume and Control System are designed to pressures less than 1000 psig and were fabricated to the requirement _ of the 1955 edition of the American Standard Code for Pressure Piping, ASA B31.1.
As a minimum, 20% of the shop and field fusion-welded butt joints were 100% radio-graphically examined. Acceptance criteria was in accordance with B31.1.
Question 1(d)
Facilities having previously experienced cracking in identified systems, (1), are requested to identify (list) the new materials utilized in repair Item or replacement on a system-by-system basis.
If a report of this information and that requested above has been previously submitted to the NRC, please reference the specific report (s) in response to this Bulletin.
Response
Two elbows on a boric acid pump suction line were observed to be cracked in April 1977 and subsequently repaired. The schedule 10 boric acid pump suction piping was completely rc placed during the November,1977 refueling outage with Type 304 Stainless Steel Schedule 40 piping. Additional information has been provided in LER 77-4/lT and the followup report, R. H. Graves letter to B. H. Grier dated March 26, 1979.
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's due,3..-tu J6N 2 61373 Origli.nl ATTACHME... A 9.C 0A l
.aple Point Date Time ph Cond Cl Boron Fe Ua Cr Mn y-Scan Perforned By 1
12/8'/78 1000 4.4 7.7
'< 03 2490
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<. 0 2 2
12/19/7f 0930 6.6 27
.08 650
.37 2.5
< 02
<.0 y
LMD, JW, WL
< 02 LM D',
JW, WL 3
12/7/78 1100 4.7 7.05
<.03 2376
.12
<.02
<. 0 2 g
<.0?
4 12/8/78 0830 4.6 7.05
- .03 2436
.32
<.03
<. 0 2 g
LMD, JW, WL 5
12/8/78 1000 4.6 7.5
<.03 2449
.20
.03
< 02
.02 v
LMD, JW, WL 6
12/8/78 0730 5.1 10.3
.03 2274
.08
.10
< 02
<.02 v
LMD, JW, FL
~
f 12/8/78 1000 5.2 16.7
.03 2346
. 12
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<. 0 2
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v
.03 403
.27
.04
<. 0 2
<.02 8
12/8/78 0830 6.45 15.5 v
LMD, JW, WL 9
Unabl to of tain "sanple 10 12/8/78 1200 3.70 49
.03 2376 l'.57
.02
<. 0 2
<.02 v
LMD, JW, WL 11 12/8/78 0830 5.9 4.2
,'0 3 1023
.16
.02
<. 0 2
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12 Un ble to ot tain sanple ca L2/8/78 1100 4.55 8.95 13
.03 2418
.17
.03
< 02
<.02 v
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.03 470
.14
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<. 0 2
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.36 2315
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f Connecticut Yankee Surveillance Procedure No. SUR 5.4-26 Chemistry D
D INSERVICE INSPECTION CHEMICAL WO
^
SAMPLING PROGRAM o'
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Q 1.0 PURPOSE 1.1 The purpose of this procedure is to establish an approved program for sampling frequency and tests to be done on systems as designated by the Connecticut Yankee ISI Coordinator.
2.0 APPLICABILITY 2.1 This procedure applies to but is not limited to the Systems Listed in Table I.
3.0 REFERENCES
3.1 PM 9.4-2.1, Ph Det'ermination 3.2 PM 9.4-2.2, Conductivity Decemination 3.3 PM,9.4-2.3, Chloride Decemination by Mercuric Nitrate Method 3.4 PM 9.4-2.16, Boron Decemination - Mannitol Titration 3.5 PM 9.4-2.25, Metal Decemination by Atomic Ab orption 3.6 CHDP 2.17. Total Iron Detemination 3.7 PM 9.4-5.5, Liquid Radioactivity Determination of Liquid 4.0 RESPONSIBILITIES 4.1 It is the responsibility of the Chemistry Technician to follow this procedure.
4.2 It is the-responsibility of the Chemist to review the results and report findings to the CY ISI Coordinator.
5.0 PROCEDURE' 5.1 Frequency 5.1.1 The systecson Table I should be sampled and evaluated:
Page 1 of 8
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SUR 5.4-26 Original JAN 2 61979 5.1.1.1 Approximately 6 mon Gs after refueling shutdown 5.1.1.2 One to two weeks before refueling shutdown.
5.1.1.3 Containment sump sampling donc during refueling shutdown.
5.1.1.4 As requested by ISI Coordinator and Plant conditions.
5.2 A Ph determination should be doce on the sample according to PM 9.4-2.1.
5.3 A conductivity determination should be done on the sample according to PM 9.4-2.2.
5.4 A chloride determination should be done on the sample according to PM 9.4-2.3.
5.5 A boron determination should be done on the sample according to PM 9.4-2.16.
5.6 An Iron determination should be done on the sample according to CIIDP 2.17.
5.7 Sodium, Chromium and Manganese determination should be done on the sample according to PM 9.4-2.25.
5.8 A T scan should be done en the sample acecrding to FM 9.4-3.3.
5.9 Record the results on Attachment A.
e Page 2 of 8 i'*
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SUR 5.4-26 Original JAN 2 6 673 TABLE I SAMPLE POINT f
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DESCRIPTION LOCATION FIG.
1 RWST Purification Pung 3
2 Containment Sump Containuent Sump 3
3 Core Deluge Cont. Lower Level Outer 3 Annulus RH-V-805 4
HPSI Recirculation HPSI Cubicle 3
5 LPSI from RUST to PAB Pipe Trench 3
Reactor Vessel 6
RHR Inlet Sample Sink 1, 3 7
RHR Outlet.
Sample Sink 1, 3 8
Chg. Pump Disch.
Sample Sink 1, 3 and Loop Pill 9
Piping Between BAMT Boric Acid Strainer 2
and Metering Pump Behind BAMT 10 Piping Between BAMT Suetiori Boric Acid 2
and Chg pumps Pump Behind BAMT 11 Boric Acid Blender Down Stream of Borie 2
to RWST Acid Blender 12 Drain hdr. from Sample Sink
1; 2 Loops and PZ to VCT
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and.PDT 13 Loop 1 RHk Return Cont. Lower Level 3
Outer Annulus RH-V-779 14 Reactor Containment Cont. Lower Level 3
Spray Outer Annulus RH-V-805
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15 Containment Sump "A" RHR Heat Exchanger 3
to RHR Cubicle Q9 0
D co' grpr gl }[
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Page 3 of 8 g
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