ML20199F695

Submits Request for Relief from ASME Section XI Inservice Testing Valve Program to Extend Interval Between Disassembly of Check Valve,Within Group of Four Similar Check Valves for EECW Dgs,From 18 to 24 Months

ML20199F695
Person / Time
Site:	Browns Ferry
Issue date:	01/08/1999
From:	Abney T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-89-04, GL-89-4, NUDOCS 9901220022
Download: ML20199F695 (13)

Text

.

t Tennessee Valley Authority, Post office Box 2000, Decatur, Alabama 35609-2000 January 8, 1999 10 CFR 50.55a (a) (3) (i)

U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 r

BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 -

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE TESTING, VALVE PROGRAM - REQUEST FOR RELIEF, PV-38 i

In accordance with 10 CFR 50.55a (a) (3) (i), TVA is submitting a request for relief to the BEN ASME Section XI Inservice Testing (IST), Valve Program.

This request for relief seeks to extend the interval between disassembly of a check valve, within a group of four similar check valves for the Emergency i

Equipment Cooling Water for the Units 1 and 3 Diesel Generators, from 18 to 24 months.

The guidance provided in Generic Letter 89-04, " Guidance On Developing Acceptable Inservice Testing Programs," acknowledges the potential for extension of the valve disassembly / inspection interval provided the extension is supported by actual in-plant data from previous testing.

The enclosed request for relief provides the required justification.

The Code of record for the BFN IST Valve Program is the 1989 Edition of the ASME Section XI Code.

In addition, TVA is using the ASME/American National Standards Institute Operations and Maintenance (OM) Standards, Part 10,

" Inservice Testing of Valves in Light-Water Reactor Power Plants," (OM-10).

t 9901220022 990108 ~~Q d

PDR ADOCK OSOOO259o fs-i{

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U.S. Nuclear Regulatory Commission Page 2 January 8, 1999 TVA requests approval of Request for Relief PV-38 by October 1, 1999, to support the next Diesel Generator Maintenance Outage scheduled for November 1999.

There are no commitments contained in this letter.

If you have any questions, please telephone me at (256) 729-2636.

S)ncere l

i i

T.

E. Abney Manager o-censin and I ustry Affai s Enclosnre j

p cc: (Enclo rc).

Mr. Harold O. Christensen, Branch Chief l

U.S. Nuclear Regulatory Commission l

Region II 61 Forsyth Street, S.W.

Suite 23T85

(

Atlanta, Georgia 30303 l

l NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 l

Mr. L. Ragahavan, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North l

11555 Rrckville Pike l

Rockville, Maryland 20852

s s'

=

ENCLOSURE TENNESSEE VALLEY AUTHORITY t

BROWNS FERRY NUCLEAR PLANT (BFN)

AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, INSERVICE TESTING, VALVE PROGRAM (SECOND INSPECTION INTERVAL)

REQUEST FOR RELIEF (See Attached)

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TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT.(BFN)

ASME SECTION XI, INSERVICE TESTING, VALVE PROGRAM (SECOND INSPECTION INTERVAL)

REQUEST FOR RELIEF PV-38 i

l l

EXECUTIVE

SUMMARY

In accordance with 10 CFR 50.55a (a) (3) (i),

TVA is proposing an alternative to the testing requirements for check valves (ASME/ ANSI OMa-1988 addenda, Part 10).

1 l

It is requested that the interval between sample disassembly of each check valve within a group of four be extended from 18 to 24 months.

NRC Generic Letter GL 89-04, l

Iosition 2, allows sample disassembly of similar check valves on the basis of one valve per group of four valves every refueling outage (based on an 18 month operating cycle).

TVA has previously l

submitted Request for Relief PV-14 by i

letter dated October 29, 1993, and received l

NRC approval by letter dated May 16, 1995.

1 This relief request stated that the check valves for the Emergency Equipment Cooling Water supply for the Unit 1 and Unit 3 Diesel Generators would be disassembled on l

a one valve per operating cycle (18 months) basis.

GL 89-04, Position 2, states that the one valve per 18 month refueling outage L

frequency may be extended to one valve per l

24 month refueling outage frequency with appropriate justification.

This request for relief presents justification for extending the frequency of disassembly of one valve per 18 month operating cycle to one valve per 24 month operating cycle.

UNIT:

BFN Unit 0 (The valves in this request for relief are common to all three BFN units) i IST INTERVAL:

Second ASME Section XI Inservice Testing (IST) Interval for Valves, (Start Date:

September 1, 1992)

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SYSTEM (S)::

. Emergency Equipment Cooling Water (EECW)

(System 67)

COMPONENTS:-

EECW:to Unit 1 Diesel Generator-Cooler i

check valves 0-CKV-67-507, 508, 514, 515,

'521, 522, 528, 529, 624, 625, 627, 628, 630, 631, 634, 635 EECW to Unit 3 Diesel Generator Cooler L

check valves 3-CKV-67-693, 694, 695, 696, i.

703, 704,.705, 706, 713, 714, 715, 716, l

723, 724, 725, 726-DRANING(S):

1-47E859-1 (Unit 1/2), 3-47E859-2 (Unit 3) j (Copy Attached) l'

.ASME CODE

. CLASS:

3 ASME CODE EDITION:

ASME Section XI, 1989 Edition, no Addenda and ASME/American National Standards i

Institute Operations and Maintenance (OM)

Standards, Part 10 f.

s CATEGORY:

C l

l FUNCTION:

Pass rated cooling water flow for the Unit 1 and Unit 3 Diesel Generator engines

{

(Open Position);' Prevent backflow from the

]

opposite EECW header (Closed Position)

ASME CODE L

REQUIREMENT (S) :ASME/ ANSI OMa-1988 addenda, Part 10, Paragraph 4.3.2 requires that check valves be exercised to the position required to i

perform their intended function at least every refueling outage.

As an alternative, l

(Paragraph 4.3.2.4.c) check valves may be disassembled each refueling outage to verify operability.

GL 89-04, Position 2, allows similar check valves to be considered in groups of four (maximum) with l

a rotating disassembly of one valve per group each refueling outage (based on an 18 l

month operating cycle).

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Q oASME CODE L

REQUIREMENT I

FROM WHICH RELIEF ISL

= REQUESTED:

Relief.is requested from the testing requirements'for check valves (ASME/ ANSI l

OMa-1988 addenda, Part 10, paragraph 4.3.2.4.c).

It is requested that the

' interval between sample disassembly of each check valve within a group of four be extended from 18 to :24 months.

i l

BASIS FOR RELIEF:

The valves are verified open quarterly by flow testing.

System design prevents the valves from being verified closed by reverse. flow.

Each diesel generator cooler supply line utilizes two check valves in series without an intermediate tap.

Attempts to detect closure of these check valves with non-intrusive test methods have l

been unsuccessful.

The isolation valves used to force the valves closed are not L

capable of quick opening or closing (the

-valves have handwheel operators).

This means that most of the check valve disks L

contact-their seat lightly,-generating insufficient noise to be detected by an acoustic monitor.

The valves also utilize a soft-seat' sealing material which dampens I

seat contact noise.

Noise in the system masks whatever closing signals are generated,.and the close proximity of the

~ series check valves would make it extremely i

difficult to identify closure of individual j

check valves in the'best of conditions.

1 The test equipment purchased to perform non-intrusive testing cannot obtain an ultrasonic trace of disk position for stainless steel check valves, which includes these check valves.

Non-intrusive u

testing of these valves has, therefore, i

been determined to be impractical due to L

the inability to obtain repeatable acoustic and ultrasonic signals.

Radiography has

[

also been determined to be impractical i3 after a review of test shots on similar 1

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check valves.

The radiographs that were reviewed did not reveal sufficient detail to determine valve closure.

Test equipment for detecting disk position using magnetics has not been purchased and was therefore unavailable for use in determining feasibility.

Since these check valves were changed from carbon steel to stainless steel material in the mid-1980's, none of the valves have failed a visual inspection during periodic disassembly.

Through the Unit 2 Cycle 6 l

(May 1993) refueling outage the check valves were disassembled and inspected once per operating cycle.

After the Unit 2 Cycle 6 refueling outage, the check valves were grouped in groups of four in accordance with Generic Letter 89-04 Position 2.

Since this was done, at least one check valve from each group has been disassembled and inspected on a rotating basis during each operating cycle.

Inspection results have detected only slight discoloration of the valve disks.

No corrosion, pitting, or other adverse conditions have been detected.

The only maintenance required on the valves is an occasional replacement of the closure assist spring.

Per the vendor, this spring is not required for the valve to close in liquid service under backflow conditions.

Free motion of the valves has been unimpeded in all cases.

A review of the Equipment Performance and Information Exchange (EPIX) System, previously the Nuclear Plant Reliability Data System (NPRDS), for this type of check valve has determined that there have been no failures of valve function for this type and size of check valve in this particular application.

The only failure listed for this particular application and type was for a broken closure assist spring.

A review of the Electric Power Research Institute (EPRI) Application Guide for Check Valves in Nuclear Power Plants for E-5 1

s location-related problems has determined that there is no potential for problems resulting from the location of the valves.

There is more than enough straight pipe upstream of the valves to preclude any turbulent flow concerns.

The flow velocities in the system are appropriate for this type of check valve.

Extension of the inspection frequency for any particular check valve in a group is consistent with Generic Letter 89-04 Position 2, currently contained in NUREG-1482, provided (1) the NPRDS database is searched for similar valves, (2) the location of the valves is addressed with regard to the EPRI Guide for Check Valves in Nuclear Power Plants and (3) the disassembly of the valves is documented in detail regarding condition and ability to full-stroke.

Previously, BFN has disassembled these check valves on a once per operating cycle frequency in accordance with Request for Relief PV-14.

With a yearly diesel generator outage, disassembly of the check valves once per operating cycle was easily incorporated into the diesel maintenance outages.

BFN has recently changed the schedule for diesel generator maintenance outages from an annual to a biennial frequency.

This i

means that in order to perform check valve disassembly, the affected diesel generator must be made inoperable for approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (minimum) every other operating cycle.

This reduces the diesel generator availability and does not provide a compensating increase in the safety of the plant (based on the inspection results of the check valves to date).

ALTERNATIVE REQUIREMENTS:

These check valves will be grouped (4 valves maximum) according to design and service conditions and disassembled on a rotating basis in accordance with Position 2 of NRC Generic Letter 89-04 with the exception that the interval between inspections will be scheduled with the l

diesel generator maintenance outages E4

I o

e (biennially).

This will extend the current inspection interval from once every 18 months to once every 24 months.

Therefore, each valve will be inspected at least once every eight years instead of every six years.

Based on the inspection results of the check valves to date,..as described above, this interval extension provides an acceptable level of quality and safety.

If a check valve selected for disassembly

{

fails the criteria of GL 89-04, then an evaluation will be performed promptly (generally by the end of the shift during which the failure occurs) to determine the failure mechanism and the likelihood that the remaining valves in the test groap are affected significantly by this mechanism.

{

The remaining check valves in the affected test group will be disassembled and inspected per GL 89-04 Position 2 criteria using the guidance of GL 91-18.

The remaining valves in the test group will be disassembled within a time frame determined by the failure mechanism evaluation.

IMPLEMENTATION SCHEDULE:

This request for relief is applicable to the Second Ten-Year Interval for the BFN Inservice Testing (IST) Program for valves.

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