ML18139A153
| ML18139A153 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/30/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-79-17, NUDOCS 8004170079 | |
| Download: ML18139A153 (35) | |
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- e Attachment
-.L-VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station Units 1 and 2 Response to IE Bulletin 7q-17
2 -
NRC ACTION ITEM
- 1.
"Conduct a review of safety related stainless steel piping systems within 30 days of the date of this bulletin to identify systems and portions of syste~s which contain stagnant oxygenated borated water.
These systems typically include ECCS, decay/residual heat removal, spent fuel cooling, containment spray and borated water storage tank (BWST-RWST) piping. II
RESPONSE
Review of the safety related stainless steel piping systems at Surry Units 1 and 2 indicates that portions of the following systems potentially contain stagnant oxygenated borated water during plant operations:
- Inside Recirculation Spray (_RS)
- Outside Recirculation Spray (_RS)
- Residual Heat Removal (RH)
Chemical and Volume Control (CU)
Low Head Safety Injection (_SI)
- High Head Safety Injection (_SI)
- Spent Fuel Pit Cooling/Purification (JP)
A listing of affected lines in the above systems is given in Attachment A to this letter.
Portions of systems given in Attachment A are shown on the following drawings:
UNIT 1 11448-FM-lOlA 11448-FH-104A 11448-FM-lOSB 11448-FM-106A 11448-FM-106B 11448-FM-106C 11448-FM-SlA UNIT 2 11548-FM-lOlA 11548-FM-104A 11548-FM-lOSB 11548-FM-106A 11548-FM-106B
3 -
NRC ACTIOil' ITEM
- 1.
(a)
"Provide the extent and dates of the hydrotests, visual and volumetric examinations performed per 10 CFR 50.55a(g) (RE: IE Circular 76-06 enclosed) of ideuti+/-iea systems.
Include a description of the nondestruc-tive examination procedures, procedure qualifications and acceptance criteria, the sampling plan, results of the examination and any related corrective actions taken"e
RESPONSE
Attachment A to this letter indicates the extent and dates, where applicable, of visual and volumetric examinations performed per 10 CFR 50.55a(g) and IE Circular 76-06 ori portions of systems identified in the previous response.
Inservice inspections required by 10 CFR 50.SSa(g) as conducted in accorclance with ASNE Section XI, 1970 Edition, with Addenda through Summer 1972.
Test personnel involved with inservice inspections are certified as being qualified in accordance with SNT-TC-lA, American Society for Nondestructive Testing.
The selection of components examined is based upon Section 4.2 of the Technical Specifications in the Surry Power Station Units 1 & 2 Final Safety Analysis Report.
In accordance with VEPCO correspondence (Serial No. 345/112476, Jan. 11, 1977) to Mr. Hoseley, U.S. Nuclear Regulatory CoillIIlission, a volumetric examination per IE Circular 76-06 was performed on the Recirculation and Containment Spray System piping.
Ten welds each on Surry Units 1 and 2 we.re inspected, with preference given to welds located in low areas.
Inspections were conducted in accordance with Article 5 of ASHE Section V.
The acceptance/rejection criteria were per NB-5330~
ASME Section III, 1974 Edition with Addenda through Summer 1975.
J
RESPONSE (CONTINUED)
Both the inspections performed per 10 CFR 50.55a(g) and IE Circular 76-06 revealed no significant system flaws.
Superficial surface flaws such as arc strikes, weld splatter, rust and scale were detected and subsequently corrected.
During each subsequent refueling outage, ten different welds on the recir-culation and containment spray system piping on each unit will be examined as described in VEPCO letter Serial No. 345/112476.
I I
e 5 -
e NRC ACTION ITEl1
- 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 recirculation procedures to maintain required water chemistry wita1 respect to pH, B, CL-, F-, o2."
RESPONSE
Cher:iistry requirements and sampling frequencies associated with the lines listed in Attachment A to this letter are shown below.
Surry Power Station Technical Specifications are also listed, where applicable.
MAKEUP TO PRIMARY*GRADE WATER CHE1IT.STRY PAP-AMETER pH @ 25°C Condu.ctivity
@ 2.:i°C, µmhos Dissolved Oz, ppm CL-, ppm Suspended solid9, ppm
+
Na, ppm REQUIREMENT 6.0 - 8.0 2.0 max.
- 0.10 max.
0.15 max.
0.15 max.
<0.10
<0.01 TECHNICAL SPECIFICATION
- Weekly, and as* required to verify abnormal daily readings.
SAMPLING FHEQUENCY Daily Daily Daily Daily Weekly Local samples are taken weekly on reserve tank and/or prior to switching tanks in service.
6 -
REFUELING "WATER STORAGE TANKS CHEMISTRY PARAf1ETER REQUIREMENT pH @ 25°C 4.0 - 4.7 B, ppm 2000 min.
Cl-, ppm 0.15 max.
F-, ppm 0.15 max.
Makeup water is of primary grade.
BORIC ACID STORAGE TANKS CHEMISTRY PAR.Al1ETER B, ppm Cl-, PP!!l.
REQUIREMENT I\\,
I\\, 20,000 ppm (11.5-13 percent boric acid)_
0.15 0.15 Makeup water is of primary grade.
TECHNICAL SPECIFICATION 4.1-10 3.3-1 TECHNICAL SPECIFICATION 4.1-10 3.2-4 SAMPLING FREQUENCY Weekly Weekly Weekly Weekly SA11PLING FREQUENCY Bi-weekly Weekly Weekly
_J
e 7 -
RESIDUAL HEAT RE}10VAL SYSTEM (Sampled when system is in operation)
CHEMISTRY PAHAlfilTER pH@ 25°C Con due ti vi ty*
@ 25°C~ µmhos Turbidity, ppm B, ppm Cl, ppm F, ppm BORON INJECTION TANKS CHEHISTRY PARAMETER B, ppm Cl, ppm REQUIREMENT 4.0 - 4.5
<l to 40 1.0 max.
~ 2500 0.15 max.
0.15 max.
0.10 max.
REQUIREMENT
'\\,
'v 20,000 (11.5 - 13 percent boric acid) 0.15 max.
0.15 max.
e TEClillICAL SPECIFICATION 4.1-10 3.1-21 4.1-10 3.1-21 4.1-10 3.1-21 4.1-10 TECHNICAL SPECIFICATION 4.1-10
- 3. 3-1 SAMPLING FREQUENCY Daily Daily Daily Bi-weekly (min) 5 times/wk (min.)
5 times/wk (min*.)
5 times/wk (min.)
SAl1PLING FREQUENCY Bi-weeKly (min)
Weekly Weekly
9 -
Various Surry Power Station scheduled evolutions minimize stagnation in borated water systems.
In the "Conduct of Operation Administrative Procedures" manual, Equipment Rotation Lists specify weekly changes in equipment operation between com-ponents (e.g., pumps) in redundant systems, thus preventing long term stagnation in associated piping.
Surcy Periodic Test Procedures are also in effect which provide for periodic flushing of the containment spray systems, low head safety in-jection systems and high head safety injection systems.
Pertinent data on these flushing evolutions are listed below.
TEST APPLICABLE PROCEDURE TECHNICAL SYSTEM NO.
SPECIFICATIONS FREQUENCY Containment PT 17.1 4.5 Honthly Spray Low Head Safety PT 18.1 3.3 Monthly, Unless Injection 4.11 RCS':'..500 psi Hi.gh Head Safety PT 18.5 3.3 Monthly, Unless Injection 4.1 RCS< 1500 psi 4.11 The above flushing procedures are specifically designed to remove possible contaminants which could cause accelerated corrosion in sensitized piping.
ACCUMULATOR TANKS CHEMISTRY PARAMETER B, ppm 8 -
REQUIREHENT 1950 min.
TECHNICAL SPECIFICATION
?..1-10 3.3-1 Recirculated with refueling water storage tahk at least monthly SPEUT FUEL PIT CHEHISTRY PARAMETER pII@ 25°C B, ppn c1-, ppm REQUIREMENT 4.0 - 8.0 2000 min. during refuel i ng 0.15 max.
0.15 TECHNICAL SPECIFICATION 5.4-2
- 4. 1 -1 0 SAMPLING FREQUENCY Mon-chly SAMPLING FREQUENCY Monthly Monthly Monthly Monthly Summaries of plant chemistry data are contained in the Surry Power Station Monthly Operating Report.
I
~---------,--------- NRC ACTION
- ITEM
- 1. (c)
"Describe the* preservice NDE performed on the weld joints of identi-fied systems.
The description is to include the applicable ASME Code sections and supplements (Addenda) that were follow.ed and the accep-tance criterion."
RESPONSE
Inspections of piping and piping systems during fabrication and erection were conducted in accordance with Specification NUS-20, "Specification for Piping for Surry Power Station/1972 Extension - Surry Power Station".
Both shop and field welds were inspected during fabrication as required by USAS (ANSI) B31.1. 0-196 7, "Code for Pres sure Piping," including applicable code cases N-1 through N-7 as supplemented by Specification NUS-20.
The extent of examinations performed is summarized below for the iines listed in Attachment A to this letter:
PIPE WALL LIQUID THICKNESS/
PIPE RADIOGRAPHY PEm:TRANT EXAM SCHEDULE DIAMETER PERFORMED PERFORMED 10 S 4 in. and See Note All fillet welds smaller Below 10 Sand 6 in. and 100%
All butt and 1/4 in.
larger fillet welds 40 S 4 in. and 100%
All butt and smaller fillet welds 40 S 6 in. and 100%
All butt and larger fillet welds 80 S anci All sizes 100%
All butt and peavier.;
fillet welds.
NOTE:
Piping welds 2 1/2 in. through 4 in. Dia. on CH, RC, SI and RH systems were butt welded and 100% radiographed.
11 -
RESPONSE (CONTINUED)
Radiographic examination was performed in accordance with Paragraph 136 of B31.l.O and under the rules of Paragraph P-102h of ASME Se.ction I or Para-graphs UU51 ancl,UH52 of ASME Section VIII.
Liquid penetran t examination was peri;ormed in ac.cordance. with ASTM E-165-60T, with acceptance criteria as outlined in B31.l.O Code Case N-7, Paragraph 4 (b)_.
Pre-operational baseline examinations of Surry Unit 1 (Jl/70-3/72) arid Su:::-ry Unit 2 (11/71-11/72) were conducted in accordance with ASME Section XI, 1970 Edition includin~ the Winter 1970 Addenda thereto.
Selection of components examined was based upon Se.c tion 4. 2 of the Technical Specifications in the Surry Power Station Units 1 and 2 Final Safety Analysis Report.
The pre-operational baseline examinations performed on portions of systems lis~ed in At-cacht1ent A to this letter co.nsisted of visual and ultrasonic inspection techniques.
Refer to Attachment A for identification of those portions of systems included in pre-operational baseline examinations.
NRC ACTION I7Elf
- 1. (d)
RESPONSE
"Facilities having previously experienced cracking in identified systems, Item 1, are requested to identify (list) the new materials utilized in repair or replacement on a system-by-system basis. If a report of this inforI!lation and that requested above has been previously submitted to the NRC, please reference the specific report(s) in response to this bulletin."
The information requested appears in "Unusual Safety Related Event Report Nao USRE-S2-76-15/Stress Corrosion Cracking of Recirculation Spray Piping/November 19, 1976/Docket Nos: 50-280, 50-281/License Nos: DPR-32, DPR-37/Surry Power Station," transmitted to Mr. Norman C. Moseley (USNRC) by VEPCO letter Serial No. 308A dated November 22, 1976.
Material substitutions were not made during system repairs and piping replacement.
I A TI AC HMEN.T 11A II (21 Pages)
UNIT 1 SYSID1:
CONTAINMENT' SPRAY DRAWINGS:
11448-FM-84A, FM-101A NOTES: 1.) Data for% inspected not completed for Unit 1 Outages 3 & 4 1 of 21 Ot..itaae Dates Unit l
- 1) 10/74 - 1/75
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- 3) 10/76 - 1/77
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19 of 21 UNIT 2
OUtace Dates Uzi.it 2 SYSID-1:
eves TO REACTOR CAVITY PURIFICATION SYSTEM
- 1) 4/75 - 6/75 DP.Aw"INGS:
11448-FM-llSA
- 2) 4/76 - 6/76
- 3) 9/77 - 10/77
- 4) 2/79 -
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l 20 of 21 UNIT 2 Unit 2 SYSTEH:
LOW HEAD St
- 1) 4/75 - 6/75 DR~"INGS:
11548-FM-89A, B
- 2) 4/76... 6/76
- 3) 9/77 - 10/77
- Inspected during preoperational baseline examinations.
- 4) 2/79 -
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21 of 21 UNIT 2
Out.ace Dates Unit 2 SYS'ID1:
- 1) 4/75 - 6/75 DPAWINGS:
11548-FM-89~, B
- 2) 4/76 - 6/76
- 3) 9/77 - 10/77
- Inspected during*preoperational baseline examinations.
- 4) 2/79 -
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