NRC-89-0106, Forwards Addl Info Re Util 880805 & 890427 Responses to Generic Ltr 88-01,per NRC 890316 Request.Util Accepts All Staff Positions Except on Water Chemistry & Insp Schedules

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Forwards Addl Info Re Util 880805 & 890427 Responses to Generic Ltr 88-01,per NRC 890316 Request.Util Accepts All Staff Positions Except on Water Chemistry & Insp Schedules
ML20246P748
Person / Time
Site: Fermi 
Issue date: 05/12/1989
From: Sylvia B
DETROIT EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-89-0106, CON-NRC-89-106 GL-88-01, GL-88-1, NUDOCS 8905220275
Download: ML20246P748 (34)


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B. R;lph Syl7b semor Vice President Detroit 6

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ISOn Newptwt, Michigan 48166 (313) 58E4150 i

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l May 12,1989 NBC-89-0106 U. S. Nuclear Regulatory Commission

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Attn: Document Control Desk 1

Washington, D. C.

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References:

1) Fermi 2 I

NIC Docket No. 50-S41

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NRC License No. NPF-43 2)

NIC Generic Letter 88-01, "NBC Position on IGSCC In BWR Austenitic Stainless Steel Piping", dated January 25, 1988

3) Detroit Edison Letter to NIC, " Response to NTC Generic Letter 88-01", NBC-88-0191, dated August 5,1988 l

4)

NIC Letter to Detroit Edison, " Fermi Nuclear Power Plant, Unit 2, Generic Letter 88-01 Response -

Request for Additional Information (FA1) (TAC No.

69135)," dated March 16, 1989

5) Detroit Edison to NBC Letter, " Revised Response to j

NRC Generic Letter 88-01," NIC-89-0088, dated

)

April 27,1989 l

Subject:

Submittal of NBC Requested Additional Information on Generic Letter 88-01 Detroit Edison has reviewed the NRC Request for Additional Information (RAI) on the Generic Letter 88-01 and our response to RAI is provided as an enclosure to this letter.

l The enclosure provides Detroit Edison's response to each specific item of the RAI, and contains additional information on the Generic Letter W

8905220275 890512 I

DR ADOCK 05000341 p

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6 USNRC May 12, 1989 NBC-89-0106 Page 2 as requested. A copy of this response has also been sent to Viking Systems International as instructed in your letter.

If you have any questions, please contact Mr. Girija Shukla at (313) 586-4270.

Sincerely, Enclosure l

cc: Mr. A. B. Davis Mr. R. C. Knop Dr. A. A. Lakner (Viking Systems International)

Mr. W. G. Rogers Mr. J. F. Stang l

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- USNRC May;12,:1989 NRC-89-0106.

Page 3-l, I, B. RALPH SYLVIA, do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the

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.best of my knowledge and belief.

$O B. PAI@H Sp#IA Senior Vice President M

On this day of W

, 1989, before me personally appeared B.- Ralph Sylvia,'tging first duly sworn and says 1

. that he executed the foregoing as his' free act and deed.

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& E dt. 0&ur M Notary Public 1'j l

ROSAUE A. ARMETTA NotoryPublic, Monroe County h4

&#CommisionEpusJan.11,1992 1

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- 3' Encloruro to a

LNRC+89-0106

.- Pags 1 Response to NRC Request for Additional Information

.I on Generic Letter 88-01' i

l The Detroit Edison's response to each NRC Request for Additional Information (RAI) item is given below:

o NRC RAI Item No. 1 Position on NRC Staff Positions J

Generic Letter 88-01 states on page 3:

~

" Pursuant to 10 CFR 50.54(f), you, as a BWR operating reactor licensee

.or construction permit holder, are requested to furnish, under oath or affirmation, your current plans relating to piping replacement, inspection, repair and leakage detection. Your response should indicate whether you intend to follow the staff positions included in this letter, or propose alternative measures."

The staff positions outlined in Generic Letter 88-01 include positions on:

(1) Materials, (2) Processes, (3) Water Chemistry, (4) Weld Overlay, (5) Partial Replacement, (6) Stress Improvement of Cracked Weldments, (7) Clamping Devices, (8) Crack Evaluation and Repair Criteria, (9) Inspection Method and Personnel, (10) Inspection Schedules, (11) Sample Expansion, (12) Leak Detection and (13)

Reporting Requirements.

Please supply information concerning whether the licensee: (1) endorses

~

these positions, (2) proposes alternate positions, exceptions, or provisions and (3) is considering or planning to apply them in the future. Please describe any alternate positions, exceptions or provisions that are proposed.

j Please supply this information using a table such as that illustrated in the example shown in Table 1.

Detroit Edison Response:

This information is provided, as requested, in Table 1.,

Detroit Edison accepts all staff positions except on water chemistry and inspection schedules. We request an alternate position on water chemistry, and accept inspection schedules with provisions as follows:

(a) The Alternate Position requested regarding the Staff Position on Water Chemistry was described in Reference 5 and is discussed below.

Recent industry experience has shown a higher fuel cladding corrosion rate and higher cladding copper concentration at a plant with Admiralty metal condenser tubes.

After preliminary evaluation of the data by the NSSS vendor, the combined effects of hydrogen and copper are thought to be the cause of this phenomenon. High copper concentrations in the crud deposit can be linked to an increased potential for clad corrosion.

1

Enclosure to NRC-89-0106 Page 2 The Fermi 2 main condenser tubes are made of Admiralty metal, except for the outer rows and air cooler sections, which are 70/30 copper / nickel. Based on this recent industry operating experience, the potential exists to increase the corrosion of the Fermi 2 fuel cladding if plans to implement Hydrogen Water Chemistry are pursued. The Fermi 2 NSSS vendor recommends deferring the mini-test until more information is known.

Deti'oi t Edison does not believe it prudent to take actions which may increase cladding corrosion and possibly lead to fuel failure, though fuel failures directly attributable to hydrogen injection i

have not yet been identified elsewhere. Crud Induced Localized Corrosion (CILC) is a recognized cause of fuel failures and actions which increase local deposition of copper would not be wise. Therefore, the mini-test will not be performed prior to the refueling outage, and Hydrogen Water Chemistry will not be implemented. This decision may be revisited, depending on future industry experience with Hydrogen Water Chemistry.

Detroit Edison will continue to take actions to maintain primary coolant water chemistry within the BWR Owners Group Guidelines for mitigation of IGSCC (Intergrannular Stress Corrosion Cracking).

(b) The provisions of Inspection Schedules as stated in Item 2 on page 3 of the original response (Reference 3) are provided below:

"As recommended, a minimum of 25% of the Category 'A' welds, 50%

of the Category

'B' welds and all Category 'G' welds will be inspected as directed within the first ten year (120 month) inspection cycle. All Category 'G' welds will be inspected at the first refueling outage at which time the welds will be upgraded to Category

'D'."

" Detroit Edison performed IHSI to 79 welds prior to plant operation in July 1983 Selected welds were reinspected in accordance with proposed Code Case N-333 This was sufficient and acceptable for a new plant as discussed in Reference 2.

Therefore, all welds treated by IHSI have been considered as Category

'B'."

- +. :Enclosura to NRC-89-0106 l?

Pcga 3 l

o NRC RAI' Item No.'2. Inservice Inspection Program

' Generic Letter'88-01 requests on page 3:

"Your current plans regarding pipe replacement and/or other measures taken or toLbe taken to mitigate IGSCC and provide

' assurance of continued long-term integrity and reliability."

"An Inservice Inspection Program to be implemented at the next refueling outage for austenitic stainless steel piping covered under the scope of this letter that conforms to the staff positions on inspection schedules methods and personnel and sample expansion included in this letter."

l 1

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The information pertaining to the pipe replacement and other mitigating actions, as well as the Inservice Inspection Program provided in most of the licensee submittals, were either incomplete or did not provide the background data that is needed to evaluate the ISI Program, such as (1) reasons / justification for IGSCC classification of welds, (2) methods, personnel qualification, schedules and identities of welds inspected and (3) results of previous inspections and/or identities of welds to be inspected during future inspections.

.Thus, the following information is requested:

1.

A listing of all welds by system, pipe size, configuration (e.g., pipe to elbow,. pipe to. valve, etc.), drawing number (piping ISO with weld I.D.), location (i.e., inside or outside of containment, etc.), weld I.D. number and IGSCC classification (i.e., IGSCC Category A, B, C, D, E, F and G).

2.

Reason / justification for the classification of each. weld, using such information as (a) weld history, such as heat sink welding (HSW),'(b) pipe and weld metal compositions or material identities to show either conforming material or non-conforming' material, (c) mitigating treatment'(s) applied such as solution heat treating (SHT), stress improvement (IHSI or MSIP).

3 Identity of welds to be inspected during past and future refueling outage.

Include (a) dates and results of previous inspections, (b) flaw characteristics including orientation l

j

3-

- +. Enclo;ura to 1

.NRC-89-0106 i

Pags 4 (axial or'circumferential), maximum length, maximum depth, repairs and/or. mitigating treatments applied.

Please supply this information in tabulary form using formats such as.that illustrated in Tables 2 and 3 i

Detroit Edison Response:

This information is provided, as requested, in Tables 2 and 3. 'IGSCC Category G ANSI B31.1 welds (weld I.D. numbers 1

FW-N21-3109-18WO through SW-N20-03-B013-FWSE) listed on I

pages 17 and 18 of Table 2 and on pages 28 and 29 of Table 3 have been added to the welds listed in the original submittal. This is due to the presence of stainless steel j

safe-ends on the non-safety related feedwater inlet and l

outlet nozzles. All of the feedwater system piping and feedwater heater nozzles are carbon steel. No inspections have been performed on these welds and Tables 2 and 3 provide a complete listing of welds as requested.

o NRC RAI Item 3 Welds Covered in Licensee Submittal Generic Letter 88-01 (on page 2) states:

"This Generic Letter applies to all BWR piping made of austenitic stainless steel that is four inches or larger in nominal diameter and contains reactor coolant at a temperature above 200 F during power operation regardless of Code classification.

It also applies to reactor vessel attachments and appurtenances such as jet pump instrumentation penetration assemblies and head spray and vent components."

Were any welds that fall within this defined scope excluded from the licensee submittal (for example, welds in the RWCU outboard of the isolation valves)? If previously excluded, please list identity of such welds and plans for mitigation and inspections in Tables 2 and 3 or provide alternative proposal.

If IGSCc susceptible welds were excluded from the licensee submittal based on temperature considerations please identify the welds and describe in detail the method of temperature measurements.

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Enclosura to NRC+89-0106 Pags 5 Detroit Edison Response:

The welds added in this submittal are located outboard of the i

outermost feedwater isolation valves. The welds are listed in Tables 2 and 3'as requested.

o WRC RAI Item 4 Welds that are not UT Inspectable Generic Letter 88-01 (in Table 1) states:

" Welds that are not UT inspectable should be replaced, " sleeved", or local leak detection applied. RT examination or visual inspection for leakage may also be considered."

Does the licensee submittal include discussions and plahs for:

a.

All welds that are inaccessible for UT insrx ; ions?

for UT b.

All welds that are only partially accessD:

inspections?

c.

Welds that cannot be UT inspected because of geometrical constraints or other reasons?

If not, please list these welds and plans for mitigation / inspection.

Detroit Edison Response:

Only two welds have been identified as being potentially partially inaccessible. These welds on the B31 Recirculation System, are SW-RD-2-A2-W20 and SW-RD-2-B2-W20. -The partial inaccessibility is due to an installed pipe whip restraint.

These welds are scheduled for inspection during RF01 (reference Table 3) and extent of inaccessibility will be determined at that time.

If any portion of the welds are determined to be inaccessible, the appropriate remedial actions, as described in Generfc Letter 88-01, will be determined at that time.

o NRC RAI Item 5 Leakage Detection Generic Letter 88-01 states on page 3: " Confirmation of your plans to ensure that the Technical Specification related to l

1eakage detection will be in conformance with the staff position

]

on leak detection included in this letter."

The staff position is outlined on pages 5 and 6 of Generic Letter 88-01 and include the following items:

1.

Leakage detection should be in conformance with Position C of Regulatory Guide 1.45 " Reactor Coolant Pressure Boundary Leakage Detection Systems," or as otherwise approved by the NRC.

2.

Plant shutdown should be initiated for corrective action when:

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l l

1

y JEnclorura to NRC-89-0106.

Page 6; a.

Within'any.24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period any_ leakage detection system indicates an increase of unidentified leakage in excess of 2 gpm or its equivalent, or b.

the total unidentified leakage attains a rate of 5 gpm or equivalent.

3 Leakage should be monitored (or determined from flow measurements if flow is continuously monitored) at approximately four hour intervals'or less.

4.

Unidentified. leakage should include all leakage other than:

a.

leakage into closed systems, or b.

leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with operations of monitoring systems or not to be from a throughwall crack.

5.

For plants operating with any IGSCC Category D, E, F, or G welds, at least one of the leakage measurement instruments associated with each sump shall be operable, and the outage time for inoperable instruments shall be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or immediately initiate an orderly shutdown.

Although most licensee submittals describe the intention of meeting some or all of these requirements or offer alternative measures, it is not always clear whether these requirements are contained in the Technical Specifications. Thus, it is requested that this information should be provided by each licensee. For clarity and completeness, please use a checklist such as that illustrated in Table 4.

o Detroit Edison Response:

This information is provided as requested in Table 4.

In addition,' conformance of Technical Specifications with NRC staff position on leak detection, as discussed in Item 4 on page 5 of our original response to Generici Letter 88-01 (Reference 3), is given below:

Detroit Edison has reviewed the " Staff Position on Leak Detection" contained in Generic Letter 88-01. As the result of our review we have concluded that the Fermi Reactor Coolant System Leakage Detection System is in conformance with Position C of Regulator Guide 1.45. _ The staff had previously accepted the Fermi leak detection design as evidenced by Section 5.2.5 of NUREG-0798.

Fermi employs a leak detection system which incorporates three distinct methods of monitoring reactor coolant leakage. They are:

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i Enclorura to

'l NRC-89-0106' i

Pag 3 7 l

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a.-

' Primary containment sump flow monitoring system which l

consists of both drywell equipment and floor drain sump I

l level and flow monitoring to determine both identified and l

unidentified leakage rates respectively.

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b.

Airborne noble gas radioactivity monitoring for diversity of detection means.

I An independent floor drain sump' level monitor which provides c.

the required leak detection sensitivity and seismic withstand capability. This monitor has been accepted by the staff as an alternative for the previously required airborne particulate monitor.

Fermi Technical Specifications for reactor coolant system leakage j

require shutdown within a 24-hour period if either the total

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unidentified leakage exceeds 5 gpm or the increase in. the rate of i

leakage exceeds 2 gpm in a four hour period. These Specifications are in agreement with the staff position. The j

drywell-floor drain level measurement system is monitored continuously and the calculation of leak rate is performed at a frequency such that a leak rate increase of 1 gpm in one hour can

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be detected.

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Unidentified leakage within the drywell is directed toward and collected solely within the floor drain sump. Thus, variation of the sump level can be used to account for all leakage except that which is contained in the drywell atmosphere. Hence, the sump level is used as the primary indication of leakage and is i

monitored directly for change by two independent systems, the level / flow monitor, and the sump level monitor. The noble gas activity. monitor indirectly monitors unidentified leakage.

1 i

Fermi has IGSCC susceptible welds which are Category G welds, as f

a result the staff position requires that at least one of the j

leakage measurement instruments associated with each sump shall i

be operable and the outage time for inoperable instruments to be limited to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or initiate an orderly shutdown.

1 The Fermi Technical Specification 3 4.4.3 complies with this l

staff position provision based on the fact that either the

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primary containment sump flow monitoring system or the drywell j

floor drain sump level monitoring system is required to be operable or the plant must be in hot shutdown with 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Either sump level i

monitor can be out-of-service for thirty days, but if both direct sump monitors are out-of-service, the plant must be in hot i

shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This specification is interpreted by Detroit Edison.to meet the staff guidance in that the sump is not allowed to be unmonitored for a period exceeding 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> without 1

being in hot shutdown.

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<Enclorurs to NRC-89-0106 Page 8 Table 1 Responses to NRC Staff Positions Licensee Response Licensee Has/Will Accept Requests with Alternate Applied Consider for l

Staff Position Accept Provisions Position

'in Past Future Use I

1. Materials X

Yes Yes

2. Processes X

Yes Yes.

F 3.-Nater Chemistry X

No Yes

4. Weld Overlay X

No Yes

5. Partial Replacement X

No Yes

6. Stress. Improvement of l

Cracked Weldments.

X' No Yes

7. Clamping Devices X

'No Yes

8. Crack Evaluation and Repair Criteria.

X No Yes

9. Inspection Method and Personnel X

No Yes

10. Inspection Schedules X

No Yes

11. Sample Expansion.

X No Yes

12. Leak Detection X

Yes Yes

13. Reporting Requirements X

No Yes

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Page 26 Table 3 Cont.

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Enclo urn to NRC-89-0106

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s-Enclorurs to NRG-89-0106

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Enclosura to 1RO-89-0106 D(agn 30 Table 3 Cont.

Notes to Table 3 NOTE 1 This column represents the NUREG-0313-Rev. 2 Required Percentage

(%) of welds to be examined over each ten year interval. The required percentage is different for each NUREG Category:

10 25% of 38 ASME III welds A =

! 40 50% of 79 ASME III welds B =

100% of 27 ASME III welds

? 27 G =

G# =

100% of 26 ANSI B31.1 welds = 26 NOTE 2 This column represents the NUREG-0313-Rev. 2 Required Percentage

(%) of welds to be examined for the First Refueling Outage.RF-01.

The required percentage is different for each NUREG Category.

2 Welds 16% (Per ASME Sect. XI)-

A

! 7 Welds B ! 16% (Per ASME Sect. XI)

G I 100% (Per NUREG-0313-Rev. 2) E 53 Welds NOTE 3 Since no IGSCC exams have been performed since the system was placed in operation, no IGSCC flaws have been detected:

Sweep-0-Let NOTE 4 SWOL

=

SE

Safe End Safe End Extension SE Ext

.y Enclosura to NRC-89-0106

'Page'31 Table 4 Detroit Edison Positions on Leakage Detection Already TS will be Alternate Contained Changed Position Position in TS to Include Proposed

1. Conforms with Position C of Regulatory Guide 1.45 Yes
2. Plant shutdown should be initiated when:
a. Within any period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or less, an increase is indicated in the rate of unidentified leakage in excess of 2 gpm, or Yes *
b. the total unidentified leakage attains a rats of 5 gpm.

Yes *

3. Leakage monitored at four hour intervals or less.

Yes *

4. Unidentified leakage includes all except:
a. Leakage into closed systems, or Yes **
b. Leakage into the containment atmosphere from sources that are located, do not interfere with monitoring systems, or not from throughwall crack.

Yes **

5. Provisions for shutdown within Yes
  • 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> due to inoperable measurement instruments in plants with Category D, E, F, or G welds.

Technical Specification 3/4.4.3 1 and 3/4.4.3.2.

Technical Specification Definitions 1.15 and 1.44.

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