ML20238F039

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Responds to IE Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. Secondary Piping Wall Thickness Exam Results Encl
ML20238F039
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 09/14/1987
From: Berry K
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
IEB-87-001, IEB-87-1, NUDOCS 8709150353
Download: ML20238F039 (22)


Text

_ - - _ - _ _ _ _, - _ _ _ _

Cy Power k Consumers Kenneth W Berry POWERlNG Director nlKN0GAN5 PROGRE55 N"d"' ""*'"s General Offmes: 1945 West Pernali Road, Jackson, MI 49201 e (517) 7881636 September 14, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

RESPONSE TO NRC BULLETIN 87-01, THINNING OF PIPE WALLS IN NUCLEAR POWER PLANTS Nuclear Regulatory Commission letter dated July 9, 1987 transmitted NRC Bulletin 87-01 and requires Consumers Power Company to provide selected information on safety-related and non-safety-related carbon steel piping systems concerning our programs for monitoring wall thickness of pipes within 60 days of receipt of the bulletin. Consumers Power Company's response for Big Rock Point is provided here1n.

Item 1 Identify the codes or standards to which the piping was designed and fabricated.

Response

The piping for the Big Rock Point Plant was designed in conformance with the Code for Pressure Piping, ASA B31.1 - 1955 Edition. The piping of concern in the bulletin was fabricated in accordance with ASTM A-106, Crade B for seamless carbon steel piping and ASTM A-234, WPB for carbon steel fittings.

Item 2 Describe the scope and extent of your programs for ensuring that pipe wall thicknesses are not reduced below the minimum allowable thickness.

Include in the description the criteria that you have established for:

selecting points at which to make thickness measurements a.

b.

determining how frequently to make thickness measurements

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OC0987-0154-NLO4 5

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Nuc1; Rrguletory Commission 2

Big-ek Point Plant Resp

%e to NRC Bulletin 87-01' September-10, 1987 c.- selecting the methods used to make thickness measurements d.

making replacement / repair decisions

Response

Big Rock Point has been testing the low quality steam lines (extraction

' steam piping and turbine drains) for many years and has replaced piping found to be out of specification. Much of the turbine drain ~ piping has been replaced with stainless steel piping which is far superior to carbon steel in erosive environments. During the last outage, a program for testing feedwater piping using the following criteria for testing was implemented:

a.

Flow disturbance, in order of decreasing importance; splitting tee, 180* bend, combining tee, orifice, 90* bend, elbow, reducer, valve, b.

Once per refueling with increasing measurements if degradation is found.

c.

Initial ultrasonic measurements are taken by the plant staff.

If abnormal degradation is detected, Laboratory Services personnel are utilized for more extensive NDT examination.

d.

Minimum wall thickness is determined by the code specified minimum-vall thickness calculation for the specific system. Repair /

replacement. decisions are based on actual wall thickness being greater than minimum wall thickness or historical wear rate projections to minimum wall thickness derived from previous inspection results.

Item 3 For liquid-phase systems, state specifically whether the fo11ow1ng factors j

have been considered in establishing your criteria for selecting points at which to monitor piping thickness (Item 2a):

a.

piping material (e.g., chromium content) b.

piping configuration (e.g., fittings less than 10 pipe diameters apart) c.

pH of water in the system (e.g., pH less than 10) d.

system temperature (e.g., between 190 and 500*F) fluid bulk velocity (e.g., greater than 10 ft/s) e.

f.

oxygen content in the system (e.g., oxygen content less than 50 ppb)

Response ~

i a.

No (all carbon. steel piping is considered).

1 l

OC0987-0154-NLO4 l

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____________________O

p., fu f

.Nucl$ar Rigul tory'Commiction L3

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Big Rock Ioint Plant q

~

Response.to NRC Bulletin 87-01

September 10, 1987 b.

Yes.(see response to item 2.a).-

j c.

No.

d.

Yes, greater than 212*F.

p e.

Considered but not given a minimum rate.

(

f.

No..

i Item 4 Chronologically list and summarize the results of all inspections that have been performed, which were specifically conducted for the purpose of identifying pipe wall thinning, whether or not pipe wall thinning was discovered, and any other inspections where pipe wall thinning was i

discovered even though that was not the purpose of that inspection.

i a.

Briefly describe the inspection program and indicate whether At was specifically intended to measure wall thickness or whether wall a

thickness measurements were an incidental determination.

J

b. ' Describe what piping was examined and how (e.g.. describe che.

inspection instrument (s), test method, reference tnia.aess, locations examined,.means for locating measurement point (s) in subsequent inspections).

j v

1 Report thickness measurement results and note those that were j

c.

identified as unacceptable and why.

l d.

Describe actions already taken or planned for piping that has t.een found to have a nonconforming wall thickness.

If you have performed a failure analysis, include the results of that analysis. Indicate whether the actions involve repair or replacement, including any change of materials.

Response

(

Big Rock Point has been testing low quality steam lines since 1970 and has replaced piping found to be unacceptable.

In 1983, the intermediate pressure extractica line was replawed from the turbine to the IP heater.

In the early.1980's, Big Rock Point also replaced much of the turbine drain piping with stainless steel due to problems encountered with pipe wall thinning of the carbon steel piping.

In 1987, a 90' elbow was i

replaced on the main steam bypass line to the condenser. Also, in 1987, a program was established to test the feedwater piping with no unacceptable thickness measurements being found.

3 OC0987-0154-NLO4 I

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NuciscrgRsgulatoryCommission:$

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Big' Rock Point. Plant-4

. Response to NRC; Bulletin 87-01:

.- Sep tember 10,,1987:

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p()'((, t

'All measurements taken on secondary side piping'have been taken for

..a.

p. y wall'. thickness inspections.. On piping included in the ISI program' thickness measurements are taken just upstream, at the' centerline and

~

4 just; downstream,-at welds.which require ultrasonic examination., No

~

' violations of minimum wall thickneiss have been found during routim W

ISI inspections.

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16: 4

b. - See attached piping [ wall thickness examination results.

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Replacements are a's ' indicated in' the attached piping wall thickness examination results.

V 1n 1987 - ?

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Thi kness measurements were'taken on'Feedwater and Main Steam M: System.'

(See first.6 pages of attachment.)

A'.1 readings were

~

acceptable?on W edwater Piping. On the Main f, team System'a 10" schedule-60 elb&w'on the bypass line was found to be'below the b

_7 i

W:

nominal wall. thickness'and-replaced (see item #5 on page 5 of the s'

. attachment).

W 5

.From 1970'to 1983 -,

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eM The turbine' drains to the lEigh pressure heater have been tested many times between 1970 andL1983. Page 7 of the' attachment shows s

ff the' replacement schedule for elbows which were found to have

. unacceptable wall thickness measurements. Due'to the frequency of replacement.of these fittings this line was replaced with m1 TN stainless steel in 1983.

Lh V

From 1980 to'1983 -

'a s

q The high pressure extraction steam line has been examined several times <for wall thickness. In 1980 elbow #,4 was replaced due to l

wall thinning (see Page 8 of the attachment).

In 1983 three elbows on the extraction line were checked and found to be t'

acceptable (pages 9 thru 13 of the attachment). -Also, during the 1983 examination of the High Pressure Extraction Line, the disc aut ou'BTV 4450 was found eroded and it was replaced with a stainless steel nut. (pages 14 and 15). Erosion of the valve body (jdasalsonoteddu{tugtheinspectionbut the valve was found to nave acceptable wall thickness.

.e '

s l

Item 5 l

Describe any plans either for revising the present or for developing new or additional programs for monitoring pipe wall thickness.

OC0987-0154-NI.04 g

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.____-_-_______-__-_-__-__0

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Nuclicr R gulatory Commission,

5

~ Big Rock Point Plant Response-to FRC Bulletin 87-01 l

. Septeraber 10, 1987 L

Response

None.

$h Kenneth W Berry-Director, Nuclear Licensing

'CC Administrator,-Region III, NRC NRC Resident Inspector - Big Rock Point Attachment OC0987-0154-NLO4

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'CONSNMERSPOWER' COMPANY)'

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NRC'Bulletin 87-01' 4

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q f A.t the'.. request of: the: Commissio'n andipursuant'to the Atomic Energy Act of 1954

[1 and. the: Energy Reorganization' Act of..1974, as :' amended', and 1the Commission's.

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Rules and. Regulations thereunder,' Consumers Power CompanyLsubmits our response

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to.NRC.Bulletin 87-01 dated July ~9, 1987, entitled, " Thinning of' Pipe Walls.in?

f Nuclear Power Plants." Consumers Power' Company's response is dated. September-1 10,:1987.

CONSUMERS POWER. COMPANY.

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.By.

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, F W Buckman, VicesPresiden Nuclear Operations' s

JSworn and subscribed to before.me this 10th day of September 1987.

utAsk Elaine E Buehrer,Motary Public Jackson County, Michigan My commission expires'0ctober 31, 1989 L

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.OC0987-0154-NLO4 L

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.j ATTACHMENT Consumers Power Company Big Rock Point Plant Docket.50-155 a

l'l SECONDARY PIPING WALL THICKNESS EXAMINATION RESULTS September 10, 1987

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14 Pages k

OC0987-0154-NLO4 i

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