ML19338D963

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IE Insp Repts 50-317/80-10 & 50-318/80-09 on 800618-20. No Noncompliance Noted.Major Areas Inspected:Qualification Data for Electrical Equipment Inside Containment as Defined in Licensee Response to IE Bulletin 79-01B
ML19338D963
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/14/1980
From: Ebneter S, Finkel A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML19338D959 List:
References
50-317-80-10, 50-318-80-09, IEB-79-01B, IEB-79-1B, NUDOCS 8009240265
Download: ML19338D963 (16)


See also: IR 05000317/1980010

Text

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

Region I

50-317/80-10

Report No.

50-318/80-09

50-317

Docket No.

50-318

DPR-53

License No.

OPR-69 ~

Priority

Category

C

--

Licensee:

Baltimore Gas and Electric * Company

P. O. Box 1475

Baltimore Maryland 21203

~

Facility Name:

Calvert Cliffs Nuclear-Power Plant Units 1 and 2

Inspection at:

Baltimore, Maryland

Inspection conducted: June 18-20,1980

Inspectors:

8I

7 //[#

A. E. Finkel', Reactor Inspector

V pte' signed

,

date signed

/

date signed

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1[N/[4d

Approved by:

/

W1

.

S.

D'. Ebneter, Chief, Engineering Support

Aat'e' signed

)

Section #2, RC&ES Branch

Inspection Summary:

Inspection on June 18-20.1980 (Report No. 50-317/80-10 ana 50-318/80-09)

Areas Inspected:

Routine, announced inspection of qualification data for the

electrical equipment inside containment associated with the Chemical and Volume

Control System, Condensate and Feed Water System, and Containment Air, Recirculation

and Cooling System as defined in' the licensee's response to IE Bulletin 79-01B

dated May 23, 1980.

The inspection involved 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> on site by one Regional

based NRC inspector.

Results:

No items of noncompliance or deviation were identified.

Region I Form -12

-(Rev. April _77).

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DETAILS

1.

Persons contacted

Baltimore Gas and Electric Company

  • R. F. Ash, Chief Nuclear Engineer

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  • D. R. Holland, Supervisor Engineering
  • R. H. Kent, Manager Electric Engineering Department

- *A. Marion, Senior Engineering Technician

  • S. A. Rittenhouse, Chief Electrical Engineer

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  • K. H. Sebra, Principai Engineer

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  • L. A. Sundquist, Supervisor Engineering Quality Assurance

- * denotes those present at the exit interview.

2.

IE Bulletin 79-018 - Qualification Data verification

The inspector on June 18-20, 1980 performed a verification inspection of

the qualification documentation of the components of the following listed

systems.

The inspection was performed in accordance with the inspection

instructions entitled " Inspection Requirements for Verifying Reactor

Licensee Responses to IE Bulletin No.79-01B."

3.

Chemical Volume Control System

The i1spector reviewed the qualification data associated with the

following in containment solenoid valves:

Plant ID Number

M_fg

Type _

ISV517

ASCO

NP8316A75E

ISV518

ASCO

WPHTX8320A21V

ISV519

ASCO

WPHTX8320A21V

ISV506

ASCO

WPHTV8320A21V

ISV515

ASCO

WPHTX8320A21V

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ISV516

ASCO

WPHTX8320A21V

a.

ISV517 Solenoid Valve - ASCO No. NP8316A75E

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-The ASCO Solenoid Valve met the following requirements as documented

in the listed documentation ASCO AQS-21678/TR Revision A, Isomedix

Inc., report covering August 1977 through January 1978, and ASCO

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Certificate of.Conformance dated November 16, 1979.

See Table 1 A.

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The above reference reports identified seven -(7) samples selected to

represent six. generic families of solenoid valves. The selected

samples were. subjected to sequential exposure of elevated . temperature, .

radiation, wear aging, seismic simulation, vibration, accident radiation,

and a loss.of coolant accident (LOCA) simulation which lasted 30 days.

The solenoid valves were energized and de-energized at high and low

presst:ce/ temperature during the test.phasa (except radiation) and

'leakt.ge from the solenoid valves was monitored.

The following. test data was reviewed by the inspector during the

review of the above referenced licensee reports:

Radiation - 50X106 rads

6

Accident' Radiation - Additional accumulated dose of 150X10 at a

dose rate of. less than 1 megarad/ hour was given to this ' family.

LOCA - The licensee used as a guide IEEE 323-1974 Figure lA. The

curve in Figure IA-1 represents the data points that the test

conformed to. The times are approximate with no intent to

reproduce the actual curve.

Thermal Aging - 2680F for 12 days.

Cycled (de-energized and

'

energized every 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). The test simulatei a 4.4 year life @

1400F (10% margin added to the 4 year design life).

.

Test sample No. 8 malfunctioned after 8 days. The valve' developed

excMsive seat leakage both in the energized /de-energized states.

At the'end of the test it was determined that the valve had dirt

in the system. -It appeared that the iron pipe used in the cylinder

)

port as . piping and a. piece of iron pipe used to-simulate an

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accumulator introduced the dirt into this system.

Wear Aging - The solenoid valve samples were electrically cycled

.40,000 times at maximum operating pressure' differential.

Baseline

and functional' tests conducted during this test _ phase of the ' test

indicates that all of the seven samples which comprise the generic

families appear to pass' the functional requirements as defined in

~ paragraphs 9.4.2.3.4 and 9.4.2.4.2 and Figure 9.1 of ASCO Quali-

fication Specification AOS-21678 Revision B Appendix A.

The'following_ items are under evaluation by the licensee:

Autmoatic Switch Company letter _of.May 2,1980 to the licensee

states for item 10NP8316A75V that the energized and de-energized

times:is 125 msec. . Test Report No.'AQS21678/TR Revision A does

not define the time requirements of the item.

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Insulation resistance measurements were recorde'd before thermal

-agire

'9t not after thisitest. The data sheets did not record

an, ,crther results for this test.

Thermal aging of this . item is based on a four year life, with

replacement of coils _and elastomeric components.

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b.

ISV518,19,15,16 and 506 Solenoid Valves ASCO No. WPHTX832021V

The ISV series of solenoid valves' part no. WPHTX832021V appears to not

,

-be qualified in the area of. radiation.

(Reference Table 1B). The

value of 10E+6 Rads.in the qualification eclumn indicates that the

data in the qualification report did not comply with the requirement

of 100E+6 Rads.

Simulated LOCA test of solenoid valves and limit switch by Nor tod

Engineering Department, itasoneilan International, Inc., dated April

19, 1973 identifies the following items and environments.

Solenoid Valve

ASCO Model WPHTX8320A21V

S/N 96578A

ASCO Model WPHTX8300BslYF S/N 96577A

Limit Switch

.

Namco fiodel No. SL3

Namco Model No. EA-740-500-00

In reviewing the qualification documentation associated witu the above

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. components the inspector identified the following areas that ceauire

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continued licensee action.

Pressure and Temperature curves are required to support analysis -

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Eastern Controls Report.

Test duration needs clarification.

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. Verification by serial number that components were subjected to a

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synergestic test programmed to be verified.

The above items are under evaluation by the licensee.

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4.

Compressed Air System

The solenoid valve ISV2085, ASCO part no. NP8320A195V meets the same

requirements as listed in Table IA of the Chemical and Volume Control

System.

5.

Condensate and Feed Water System

The components for this system were level transmitters manufactured by

Fischer and Porter part no.13D2495KBAABCB. The ID numbers for the com-

ponents are identified in Table IC.

The inspector reviewed the following test reports associated with the type

testing of this transmitter design,

a.

Ameron Report No. 1550a dated March 23, 1972

Fischer and Porter letter of March 6,1975 stated that the use of

Amercoat 66 paint is used on cast iron bases and covers of their

generic family of transmitters.

The Ameron test report no. 1550a_ qualified their Amercoat 66 paint

over cast iron to the following requirem9nts:

Temperature - 340 F

Pressure - 100psfg

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Radiation - 6.0X10 R

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Chemical Solution - Immersed

b.

Fischerand Porter Report 2204-51-B-006 dated December 1968

Fischer and Porter tested their generi: designs to the following

environments:

0

320 F = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

Temperature

29 F = 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />

22 F = 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />

150 F = post 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />

PSIA

90 = 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

60 = 1.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br />

20 = 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />

Specific components tested to the above environment were as follows:

10B2491

10B2495

13D2493

10B2494

10B2496

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.The above components were electronic differential pressure transmitters

~ (Modified as follows -l sealing and high temperature electronic

modified.

components with Amercoat'66 used on the external surfaces.)

Fischer

and. Porter informed the licensee that the 13D2495 component used at'

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the Calvert Cliffs site are the same as-the 1302493 component that was

.qualifled..

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c.

Franklin Institute Report F-C2815 dated May 1970 Entitled

" Qualification Tests of Differential Pressure Transmitter Under

Nuclear Irradiation"

3

The object of this' test was toiverify proper function of transmitters

when subjected to irradiation from a Co-60 source.

Three electronic force balance transmitter units consisting of (1) an

oscillator-amplifier module, (2) a detector coil assembly, and (3) a

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force motor. -These three transmitter types are used on F&P pressure

transmitter modules 10B2490, 50EP1000, 50EN1000, and 50ER1000.

The

measuring elements were not tested as part of-this test.

The three electronic force balance transmitters were exposed to a

Cobalt 60 irradiation as follows:

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Unit-1

53 hrs

accumulated dose of 5.7X106

  • Unit 2

48 hrs

accumulated dose of 4.2X10

Unit 3

53 hrs

accumulated dose of 2.5X106

  • Unit 2 (a detector coil assembly) was removed from the test after 48.

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hours and a complete pressure transmitter Model 1082495 with top cover

removed was irradiated'with the above source for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for an accumulated

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dose of 0.85 megarads. Thisgevel'ofirradiationdoesnotmeetthe

licensee requirements of 1X10 as required by their qualification

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requirement.

The FIRL report of May 1970 F-C2815 does not reference the serial

numbers of the transmitters tested and the F&P report 2204-51-B-006

dated December 1968 do not identify the serial numbers of the component

tested.. The licensee is to verify that the components tested in the

above' referenced reports are of the same serial number.

The licensee

also is investigating why the qualification test of the 13D2495 level

transmitter did not comply with the specification requirements.

Reference Table IC.

6.

Containment ~ Air Recirculation and Cooling System

. Joy, manufacturer of the containment tc - used a 480 Volt 75 HP Reliance

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motor part No. X324356A6W and a 480 -Volt 125 HP Reliance motor part No.

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X323727A1AW as the fan power source. The containment fan component was

qualified to the requirement-as listed in ible ID. The inspector questions

the-American Air Filter Co. test report dated April 7,1973 in the area of

motor cycles'and-synergistic testing.

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Motor Cycles - The qualification specification Bechtel No. 6750-M'-204'

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and Technical File #6750-1520 Form CC-100 Category. III for motor.

. during LOCA conditions requires that 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> cycles be required during-

the test, but- the. test was reduced to 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per cycle.

During

a site' review of the qualification data Item'159 in Audit Action

Scheduie of Licensee. dated August 1975 identified this as an unresolved

. item by the NRC.

The licensee closed this item 159, by the following statement:"the 12

hour per cycle was in error and that 3 to 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per cycle was. all

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that was required.". Reference FSAR Sections 6.5.4.f and 6.5.3.c, also

Section 14.16.. The licensee is required to provide the justification.

for the change approval,

b.

Synergistic testing and the environments ~of Table ID are to be verified

by the licensee.

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Continental Wire and Cable Company

The Continental Wire and Cable Company qualified the following type of

cables to .the environment identified in Table IE.

a.

Cable A:- 7 conductor #12 (7) copper, CC-ll5 silicone rubber insulation,

glass braid over silicone, glass finished with a flame' and abrasion

resistant finish CC-1233, mylar binder tape, overall asbestos braid,

asbestos finished with CC-ll20 flame and abrasion resistant finish,

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b.

Cable- B'_- 2_ conductor #16 (7)' copper, CC-2115 silicone' rubber insulation,

glass braid over silicone, glass braid finished with a flame and

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abrasion resistant ~ finish CC-1233, 2 conductor cabled with impregnated

asbestos fillers, mylar binder tape, overall asbestos braid, asbestos

finished with CC-1120 flame and heat resistant finish.

The qualification of these cables is documented in Franklin Institute

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Research Laboratories (FIRL) report F-C2935 entitled " Test of Electrical

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r 61es Under Simulated Post-Accident Reactor Containment Service,"

cated October 1970. This report is considered to be proprietary by the

vendor.-

Areas-that require clarification by the licensee are as follows:

1 Radiation

As identified in. Table IE the' radiation requirement is

100E+6 while the cable was tested 'to 10E+6.

Reference Industrial

Reactor Laboratories, .Inc. letter dated October 7,1970.

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-Chemical Spray' . Table IE requires a chemical' spray of 1.1% B/A.

FIRL

report F-C2935 dated October 1970 does not identify any chemical spray

test.

Both of the above items are being evaluated by the licensee.

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Anaconda Wire and Cable Co.

The following samples of Anaconda cable were qualified as identified-in the

requirements of Table IF.

Sample 1

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7 Conductor cable, No.14AWG

7 strand Anaconda; ME299

- Insulation. Individual conductors MH8100 Conductor

- Covering and.fiH8100 Belt overall.

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Sample 2 -

. Power Cable Single conductor

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AWG No. 7 wire size stranded, ME299 Insulation,

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HH8100 Belt.

The qualification of the above samples was performed by FIRL and documented

in~ their report F-C2525 dated October 1969.

The qualification program

included irradiation of'the samples with a Cobalt 60 source, a steam and

chemical spray environment and testing the insulation of the samples.at

various points in the test cycle.

During the autoclave steam test, Table

2F, the test samples had 480V applied.

Radi2 tion dose rate for the two

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sample cables was 490 MRAD from a Cobalt 60 source.

The % of B/A as listed in Table IF has to be verified by the licensee.

9.

, Licensee Event Report (LER)

As' defined in item 6 of IE Bulletin 79-01B, "the licensee is required to

submit ar. LER for any Class IE electrical equipment item which has been

determined as not being capable of meeting environmental qualification

requirements for service intended." The components identified in this

report as being investigated or to be verified by the licensee will be

required to meet item 6 of IE Bulletin 79-01B if the information in the

,

qualification _ documentation can not be verified.

10.

Safety Eveluation Report

The acceptability of qualification documentation identif'.d in this report

will be documented in the Safety Evaluation Report (SER) that is to be

written-for this' licensee. -The SER is~ planned to be issued for this site

by February 1981.

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Exit Interview

._

At the conclusion of the inspection on June 20, 1980, a meeting was held at

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the Baltimore, Maryland corporate office with representatives of the licensee.

Attendaes at this meeting included personnel whose names are indicated by

notation.(*) in paragraph'l. The inspector summarized the results of the

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inspection as described-in this report.

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Equipment

Enviroment

Qualification

Description

Parameter

Requirements

Qualifiestion

Methods

Operating Time

NA

NA

0

U

ISV517

Temperature

276 F

280 F

Sequential Test

NP8316A75E

Pressure (psig)

50

70

Humidity (%)

100

100

Chemical Spray

1.1% B/A

0.3% B/A

Radiation

100E+6

150E+6

.

Aging

4.4 years

Uperating

Requirements:

Cold Shutdown

ASCO Solenoid Valve ISV517

Table IA

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wto*FlltoNV

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asn'fllCl'H&

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ASCO Solenoid Valve 1SV517

TEMPERATURE / PRESSURE CURVE

FIGURE IA-I

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Equipment

Enviroment

Qualification

Description

Parameter

Requirements

Qualification

Methods

ISV518,519,

0parating Time

NA

NA

Synergistic Test

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515,516 & 506

Temperature

276 F

310 F

Pressure (psig)

50

65

Humidity (%)

100

w/s

Chemical Spray

1.1% B/A

6% B/A

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Radiation

1rJE+6

10E+6

Aging

l

Operating

Requirements:

LOCA, HELB, Cold Shutdown 1SV518

1SV519

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LOCA/HELB

ISV515

LOCA/HELB

ISV516

.

LOCA/HELB

ISV506

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ASCO Solenoid Valves Qualification Data

Table IB

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Equipment

Environment

Qualification

Description

Parameter

Requirements

Qualification

Methods

ID No.

Operating Time

NA

NA

ILTill3A,B C,0

ILT1123A,B,C,D Temperature

276 F

320 F

Sequential Test

Pressure (psig)

50

90

Humidity (%)

100

100

Chemical Spray

1.1% B/A

NA

Radiation

100E+6

0.82E+6

Aging

Operating

Requirements:

During LOCA and Hot Standby

,

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Fischer and Porter Level Transmitters

Qualification Data

Table IC

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Equipment

Environment

Qualification

Description ~

'osrameter

Requi rements

Qualification

Methods

ID IMB105,102 ' Operating Time

NA

NA

& 405-75HP

480 volt motor Temperature

276 F

300 F

Reliance

Electric Co.

Pressure (psig)

50

80

Part No.

X324356A6AW

Humidity (%)

-100

100

Chemical Spray

1.1% B/A

Caustic

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Radiation

100E+6

10E+8

Aging

Operating

Requirements:

LOCA, Hot Standby, Cold Shutdown

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1

Joy Containnent Fan Motor

Oualification Data

Table ID

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Equipment

Enviroment

Qualification

.

Description

Parameter

Requirements

Qualification

Methods

Operating Time

NA

NA

Caole CBLXXX

Temperature

276 F

340 F

Sequential Test

Continental

Pressure (psig)

50

100

'

Humidity (%)

100

100

Chemical Spray

1.1% B/A

B/A

Radiation

100E+6

10E+6

Aging

Operating

Requirements: During LOCA, HELB, Hot Standby and Cold Shutdown

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Continental llire/ Cable

Qualification Data

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Table IE

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Qualification

Equipment

Enviroment

_

Qualification

Methods

Description

Parameter

Requirements

Anaconda:

Operating Time

NA

NA

Cable sizes,

0

U

Nos. 14 and

Temperature

276 F

346 F

Sequential Test

7 AWG

Pressure (psig)

50

113

.

Humidity (%)

100

w/s

Chemical Spray

1.1% B/A

B/A

Radiation

100E+6

200E+6

Aging

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Operating

Requirement:

During LOCA, HELB., Hot Standby, Cold Shutdown

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Anaconda Cable Oualification Data

Table IF

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~ Autoclave Steam Test of Power and Control,

Cables Irradiated to 24 MRAD

Autclave

Current in

Current in

- Total

Environment

Pairfof Conductors

Cable.of

Elapsed Time

Pressure Temp

Sample.1

Sample 2

(Min).

(psig)

(OF)

-(Amps)

'(Amps)

Remarks

0

0

80

37.7

5.0

5

14.0-

230

37.5

5.0

10

55.0

288

37.4

5.0

Boric Ac'id

Spray Started

20

50.0

294

36.6

4.5

30

50.0

295

36.4

4.5

,

60

49.0

296

36.0

4.4

120

49.8

296

35.0

4.3

1

125

39.6

283

Steam & Boric Acid'

--

--

140

29.0

272

35.6

4.5

160

2.0

257

36.0

4.5

180

0

248

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Anaconda Cable Test Data

Table 2F .

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