ML20030A348

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Submits Addl Info to 720720 Proposed Tech Specs Change 33 Re Tech Specs Adequacy for Explosive Actuated Valves
ML20030A348
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 12/04/1973
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Skovholt D
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8101090363
Download: ML20030A348 (6)
v • d • e


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Re: License No DPR-6 1

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Mr. Donald J. Skovholt Assistant Director for

?,t Docket No 50-155 c

Operating Reactors Qc I,'y 4'^'j Directorate of Licensing g3 US Atomic Energy Commission ""

t Washington, DC 205h5 1i

Dear Mr. Skovholt:

On July 20, 1972, a Proposed Technical Specifications Change was submitted concerning the testing of the explosive actuated valves in our Big Rock Point liquid poison system. This proposal was approved as Technical Specifications Change No 33 with the condition that additional information be submitted to allow further evaluation of the adequacy of the Technical Specifications governing the testing of the explosive actuated valves. The information requested is herewith submitted. Your questions are included to provide clarity.

Question:

"Your letter stated that a temp'erature monitoring program is in progress at the Big Rock Point Plant to determine the precise environ-mental temperatures that the explosive primers experience, and that cur-rent results indicate that the primers in the equalizing line experience a temperature of about 101 F while the varmest of the other five primers experience a temperature of about 95 F.

In subsequent discussions with your staff, it was stated that the temperature environment of the primers was less than the 101 F and 95 F values. The data currently available to us are insufficient to support that the high reliability required of the explosive primers is maintained for five years if the temperature environ-ment exceeds 90 F.

It is requested that the results of your temperature monitoring program be submitted for our review together with a discussion of the quantitative reliability of explosive primers as a function of time and temperature."

Response: Temperature Monitoring Program A temperature monitoring program was established following the spring 1972 refueling outage to monitor the temperature of the two equal-izing line valve primers continuously. The initial data from this pro-gram revealed that the temperatures of the two equalizing valve primers were approximately 150 F.

The high temperatures were due to the piping g w. w g o 3 (o b G G S 0

I Mr. Donald J. Skovholt 2

~

License No DPR-6, Docket No 50-155 December 4, 1973 t

configuration which allows condensation of steam from the main steam line in the vicinity of the equalizing valves. Fans were placed in service and the temperatures of the two equalizing valve primers have ranged from about 60 F to 100 F with an occasional peak of about 110 F.

The 110'F peaks occurred during the hottest summer days. The temperatures of the remaining five explosive valves are not affected by steam condensation. These tem-peratures ranged from 10 F to 20 F below those of the equalizing line valves.

In general, these temperatures follow seasonal and daily air temperature changes in the immediate area of the valves.

The two equalizing valve primer-trigger assemblies that experi-enced the 150 F temperatures have since been replaced. The removed primer-trigger assemblies were subsequently test-fired satisfactorily.

A temperature recorder with alarm function is being purchased to monitor continuously the temperatures of the five valves that could be affected by unusual events (the two equalizing valves and three poison system outlet valves) such as valve packing steam leaks or air cooling fan failures. The temperature alarm will alert plant operators of high temperatures if they occur. Should the 120 F temperature limit be ex-ceeded, the affected valve will be replaced if required by the attached time / temperature curve.

Time Temperature Requirements Conax recommends that the maximum storage temperature of the primer chamber assembly should not exceed 120 F and that this assembly should be replaced within five (5) years after date of manufacture. This recommendation is based on Conax short-term temperature tests, information obtained from Hercules Powder Company and actual service and test data supplied by various customers. These data were used as the bases for the attached time / temperature chart.

The testing program implemented in the spring of 1972 and made a requirement by Technical Specifications Change No 33 assures that the valves that experience the highest temperatures will not be in service for periods exceeding one year. The remaining five rarely exceed 90 F and will not be in service for greater than five years following the date of manufacture. Thus, the service requirements are well within the Conax recommendations.

Question:

"Your proposed technical specification change calls for the removal of the explosive primer and trigger assembly prior to test-firing.

In general, it is desirable to perform surveillance testing of engineered safety systems or components thereof under conditions as close as practical to the conditions of actual usage.

It is requested that a discussion of the advantages and disadvantages of in-place test-firing of the explosive primers be uibmitted with a justification for your position on this matter."

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Mr. Donald J. Skovholt 3

License No DPR-6, Docket No 50-155 December k. 1973 i

Response

i Present test-firing of explosive valves is conducted as a de-structive bench test by using a primer-trigger that has been removed from service and installing it in a spare valve body with a spare inlet fitting.

The d-c current is increased in one primer bridge circuit to check the mnount of current required to fire the unit. The unit is then inspected and checked to verify that the inlet fitting cap has been properly sheared and that a second primer bridge wire is open circuited, which indicates that autodetonation occurred in the second primer.

i The installed system is designed so that a trickle current passes through the primer bridge wires at all times during plant operating condi-tions. The only drawback to this surveillance is that the contact circuits of the CVXA and CVXB relays and the contacts of hand switches 7008 and 7009, of the poison-firing circuit are not tested. The annual circuit resistance tests made by plant personnel measure switch contact resistance but not relay contacts.

This circuit resistance test has been done regularly for ten years, although it is not a Technical Specifications requirement.

A special test was developed in an attempt to perform an inte-grated operational test of the installed actuation circuitry. This test involved replacement of the primer-trigger assemblies with fuses. The test was conducted during the early November 1973 scheduled plant outage.

r The set of seven fuses simulating the B circuit blev properly.

Only one of the seven fases in the A circuit blev. The operator returned the hand switches to normal and the trickle current alarm for the A circuit cleared to indicate that the circuit was still intact. Since one fuse had j

blown, it should have indicated poison system control circuit A failure.

Inspection and testing of components did not reveal the cause of the problems and two subsequent fuse blowing tests were conducted without recurrence of the problems associated with the first test.

' Analysis indicates that the most cuspect cause of the problem is contact resistance associated with the CVXA relay. Since this relay is never exercised on a routine bases, and the current requirement in the cir-cuit is low, minor oxidation may have caused the one-time problem. This r

does not explain the alarm failure. Future testing is planned for the next cold shutdown to attempt to answer the unresolved questions and de-termine further corrective action.

Based on the results of this testing, the redundancies asso-ciated with the two parallel firing circuits, the parallel valve arrange-ments, and the trigger assembly test-firings, we have concluded that the poison system is fully operable as intended by design and reliab]e.

t Both the circuit tests using fuses as described above and the i

destructive bench tests will be conducted at regular intervals in the future. These tests thoroughly monitor system perfo~mance through valve actuation and obviate the need for in-place testing of the explosive primers.

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h Mr. Donald J. Skoiholt License No DPR-6, Docket No 50-155 December 4, 10?S Question:

"Because of the small number of test-firings and the design of the valve, deterioration of the explosive is not established by the test-firing unless very unexpected gross deterioration of the explosive occurs.

You are requested to investigate the feasibility and benefits of a more definitive testing of explosive deterioration such as measurement of energy or iepulse output."

Response

We have investigated the feasibility of a testing program that would monitor small amounts of deterioration of the explosive. In order to gain statistical significance, samples would have to be obtained at least three times a year, which would likely involve two more cold shut-downs a year than we presently experience. This program would be expen-sive both in terms of the test program cost, additional trigger assemblies costs and replacement power costs plus ftel integrity. Historically, off-gas release rates have always increased following cold shutdowns.

In addition, the present test-firing program demonstrates that sufficient degradation has not occurred to preclude proper operation of the valve.

Based on our investigations, we have concluded that the present test-firing program provides adequate assur1nce that detonation of the primers will actuate the valves and that a more definitive program of testing explosive deterioration is not warranted at this time.

Yours very truly, RBS/ map Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC i

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TRIBUTION FOR PART 50 DOCKET M.

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CONTROL NO:

8680 FILE:

FROM:

DATE OF DOC DATE REC'D LTR MEMO RPT OTIER Consumers Power Company Jackson, Michigan 49201 Ralph B. Sewell 12-4-73 12-6-73 X

TO:

ORIG CC OTIER SENT AEC FDR X

SENT LOCAL PDR Mr. Skovholt 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

XXX 40 50-155 DESGRIPTION:

ENGLOSURF5:

Ltr re their 7-20-72 itr submitting Proposed Tech Specs Change No.

33........ furnishing re< uested Addl info to Tech Specs Change No. 33 for the Big Rock Point Plant......

'l

";'t.pp m n-n M uiUn Lk ' d N0t Remove PLANT NAME: Big Rock Point FOR ACTION /INFORMATION 12-6-73 AB BUTLER (L)

SCIMENCERsL)

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/ OGC, ROOM P-506A SCHROEDER GAMMILL DIGGS (L)

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B. HURT CASE ENIGHT BALLARD COULBOURNE (L) ptgg3 GIAMBUSSO PAWLICKI SPANGLER LEE (L)

MCDONALD BOYD SHA0 MAIGRET (L)

DUBE HOORE (L)(INR)

STELLO ENVIRO SERVICE (L)

DEYOUNG(L)(PWR)

HOUSTON MULLER SIEPPARD (E)

INFO

/ SKOVHOLT (L)

NOVAK DICKER SMITH (L)

C. MILES P. COLLIUS ROSS KNIGHTON TEETS (L)

IPPOLITO YOUNGBLOOD WADE (E)

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R. DIGGS ON 12-6-73 1-GERAL7 ULRIKSON.. 0RNL 1-RD.. MULLER..F-309 C

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