ML17053D123

Forwards Request for Addl Info Re Inservice Insp Program. Response Requested within 60 Days of Receipt of Ltr

ML17053D123
Person / Time
Site:	Nine Mile Point
Issue date:	04/14/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Dise D, Seibert C NIAGARA MOHAWK POWER CORP.
References
NUDOCS 8204270472
Download: ML17053D123 (18)

Text

DISTRIBUT ION:

Docket File NRC PBR L PDR ORB¹2 Rdg Docket No.I,60-220 DEis enhut SNorris PPolk AEOD IE ACRS-10 OELD Gray File APR 1 4

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Hr. Donald P. Disc Vice President - Engineering c/o hliss Catherine R. Seibert Niagara hhhawk Power Corporation 300 Erie ':Boulevard Hest

Syracuse, New York 13202

Subject:

Inservice Inspection Program Re:

Nine Nile Point t<uclear Station, Unit No.

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Reference is made to your letters of December 9, 1976 and htay 2, 19SO in which you submitted an inspect>on program for the Nine Nile Point Nuclear Station (Unit No. 1).

He have completed our initial review and have determined that we need additional information.

This infor-mation is discussed in the enclosure to this letter and your response is requested within 60 days of receipt of this letter.

The request for information contained in this letter affect fewer than ten respondents; therefore, OhS clearance is not required ~~under'~P.

L.96-511.

Enclosure:

Request for Additional Information Sincerely, ORIGINALSIGNED BY Domenic B. Vassalle,'. Chief Operating Reactors Branch ¹2 Division of Licensing cc w/enclosure:

See next page OFFICE/

SURNAME/

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NRC FORM 318 (1040) NRCM 0240 I

OFFICIAL R ECO R D CO P Y USGPO: 1981~960

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Yir. Donald P. Disc CC:

Leonard M. Trosten, Esq.

LeBoeuf, Lamb, Leiby

& MacRae 1333 New Hampshire

Avenue, N.

W.

Suite 1100 Washington, D. C.

20036 State University College at Oswego Penfield Library - Documents

Oswego, New York 13126 Resident Inspector c/o U.S.

NRC P.O. Box'26

Lycoming, New York 13093 Carl D. Hobelman, Esq.

LeBoeuf, Lamb, Leiby 8 MacRae 1333 New Hampshire

Avenue, N.W.

Suite 1100 Wasliington, D.C.

20036 Ronald C. Haynes Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

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Encl os ure REQUEST FOR ADDITIONAL INFORMATION IHSERVICE INSPECTION PROGfVd<

Nine Mile Point I Your December 9,

1976, submittal (Reference )) stateo that your next 40-month inservice inspection period would comnence

December, 1975, would be p,eceded by appropriate technical specif',cations.chances, anc would cc-..p y w.I n the 77 edi tion (including Summer 78 aodenda

) o, Section

);I o the ASME Boiler. and Pressure Vessel Code.

However, on May 2, 1980 (Reference 2), you forwarded (as an attachment),

your September 17, 1976 ISI Proqram (Reference 3) for 120 months (75-85) interval. Therefore, does NMPC wish to make any relief reouests in addition to those in the September 17, 1976 program?

Is a

new program

.for the 79-89 interval planned as permitted by the November 1, 1979 change to

".10 CFR 50-55a?

Il.

Technical S ecifications Deviations (Reference 3, Aooendix E

Requests No. E-1. Cateqor B-A, Pressure Retainino Welds in Reactor Vessel Belt ine Re son, - not accessible, and No.

E-ategory B-B, ressure retaining l~'elds in Vessels:

Only Closure Heao Circumferen ial and Meridional Helds to be examined, corresponcing welds in reactor vessel and bottom head not accessible.

This relief request applies to the volumetric examination requirement for reactor pressure vessel pressure-retaining

welds, examination categories B-A ano B-B.

Only those welds above the.sacrificial shield are accessible for I

i..s='r ice examination.

Access has nor. been provioed in ihe sacrificial shield area for external examinations nor does the BVR design permit internal exami-nations in this area.

Only those welds above the sacrificial shield and por-tions of welds as may be accessible at nozzle access points will be examined during the inservice inspection intervals.

The following additional in ormation is requested:

(a)

Identify ihe welds that cannot be examined.

(b) identify. the welds that can be examined.

page 2

(c)

For each category estimate (1) the code-required weld length that can be inspected, (2) the code-required weld length that is inaccessible, and (3) the accessible weld length, which can be examined, but whose examination is not required by the code.

Please supply sketches and/or other information to support your estimates.

(d) is i. possible to perform surface or remote visual examination Q, os weld al eas

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i (e to volUT'e r ic exa inc'o 2.

Request Iio ~

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'allegory B-D, lUll Penetraiion fields in l~ozzles in Vessels:

tiozzle to Vessel Welds will not be examined as they are covered by non-replaceable insulation.

Recirculation inlet nozzle to vessel.welds will be examined.

Relief is requested from performing the required volumetric examinations on certain nozzle to vessel welds due to non-replaceable insulation.

The following additional information is requested:

(a) identify the speci ic welds involved and supply sketches (b)

What alternative examination methods can be performed?

!n particular, can alternative examinations of the inside su! faces be perfor

.ed?

3.

Relief Request E-4, Category B-G-l, Pressure Retaining Bolting, 2 inches and larger in diameter Pelie; is requested from perfol Ning the required volumetric exa-,i; nation -;or -ne

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vc. ives and subs c I Tu ing visual examination since non-replaceable insulation makes the valves inaccessible for volumetric and surface examinations.

b.

Relief is also requested from the required surface examination of the Closure Head studs and nuts and visual examination substituted since they have been Parkerized (corrosion treatment),

rendering surface examination results invalid.

page 3

The following additional infor'mation is requested:

(a)

Please clarify the effort required to remove the insulation and perform the required volumetric examination.

(b)

Are alternative examination techniques available for the examination of the Feedwa ter va 1 ves?

4.

Request No. E-5, Category B-H, Vessel Support Rel i e, i s requested from per, or;.1 "g he rendu e" "

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o at least 10~ of the welds to the vessel due to inaccessibility.

The following additional information is requested:

(a)

Please supply sketches and/or other information to support your claim of inaccessibility.

(b)

Are alternative examinations, such as surface, inspection, feasible?

(c)

Please provide estimates af the man-hours and radiation exposures that would be incurred in a surface examination of at least 10~> of the welds during this inspection interval 5.

Request Ho.

E-6, Categorv B-I'-I, Support hembers for P';ping, Valves and Pumps b ~

Rel ief has been requested to allow use o

a liquid penetrant examination in lieu o the required volumetric examination for the Group A integrally welded external support attachments due to geometrical considerations.

A visual examination is proposed 1>

sul face conditions cannot be made compatible

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The following additional informati on is requested:

(a)

Identify the welds that can be examined.

(b)

Identify the welds that cannot be examined.

(c)

For each category, estimate the portion o

the welds that can or cannot be examined.

(d)

Provide sketches or other documentation to justify your relief request'ue to geometrical considerations.

(e)

Have you tri ed liquid penetrant examinations?

h'hat conclusions did you reach?

page 4

6.

Relief Request E-7, Category B-L-2, Pump Bodies Relief is requested from the visual examination requirement for the internal pressure boundary surface of the recirculation pumps due to inaccessibility.

The following additional information is requested:

(a)

Please provide more detail to justify your basis for relief based on inaccessibility.

(b)

What are the radiation levels in the area of the pumps?

What '.s ihe total estimated man-rem exposure reouired to perform the examinations?

(c)

What are the manufacturer's recommendations about disassembly of the pumps for regular maintenance?

7.

Relief Request No. E-S, Category B-Yi-2, Valve Bodies Relief is requested from exami nation of the internal pressure boundary surfaces of the recirculation suction and discharge valves since inspection v ovid require draining reactor vessel water.

The following addi.ional information is requested:

(a)

Hill these valves be exam ned shoUld valve maintenance be required?

(b)

Will visual examination of thc valves be maoe when syste;,. pressure tests (IWA-5000) are conducted in accordance with the requirements for category B-P?

(c)

Has ultrasonic thickness testing been considered as an alternative mE'.ho 0?

8.

Relief Request E-g, Category B-N-l, interior of Reactor Vessels Relief is requested from the requirement for visual inspection of ihe core plate, lower core grid and liquid poison spargers because they are not accessible for visual inspection during normal re ueling outages.

The following additional info.mation is requested:

(a) is this more. appropriately in category B-N-2?

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(b) If so, is a relief request still necessary?

9.

Relief Request E-10, Category C-B, Pressure-Retainino Nozzle Melds in Vessel Relief is reouested from the requi rement to perform volumetric exami nat'ions o

the shutdown coolino heat exchanger inlet/outlet nozzle welds and insteao substitute

a. liquid penetrant examination since they are effectively non-full-penetration socket welds.

The following additional information is reouired:

(a)

Please provide sketches and/or, additional information to explain vhy these welds are "e

ec.ively" non-full-penetlation socket welds.

(b)

Please provide a list of the wclds for which relief is requested.

i 0.

Relief Request E-1 1, Cateoorv C-E-1, Support l'>embers

=or Pi pi rg, Valves and Pumps Relief may be requested from the reouirement or liouid penetrant examina-tion of the Group B integrally-w>e'.deo external support attachm>ents due to ur>ace conditions and geometrical considerations.

n visual examination may be substituted.

The following additional information is required:

(a)

Do you still wish to make this relief request?

(b) If so, for each specific item =or which relief is still reouested, please provide information to support that relief request, including:

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1.

Sketches and/or other information to support

. the=geometrical limitation claim 2.

The percent of each weld that could be examined by surface techniques.

11.

Relief Request E-12, Category C-F, Pressure-Retaining Welds in Piping,

Pumps, and Valves in Systems which Circulate Reactor Coolant Pelief is requested from the requiremen. for volumetric exam'.nation in all of the non-exempt Group B Feedwaier System (System No.'s 20, 30, 50) and s bstituiion of a hydrostatic pressure t st.

These portions

a. e covered by non-replaceable insulation and are considered inaccessible for volumetric and surface examinations.

The following additional information is requested:

(a)

Please provide additional information to support the claim that the examination requirements are impractical.

(b)

Please propose an alternate program which includes removal of a

portion of the insulation and incluoes sample examinations; Relief is requested from all examinations for portions of Feedwaier (System 50) and Cleanup (System 35) thai are in,ii..h radiation areas (demin-eral izers, filters, sludge

tanks, etc. )

The following additional information is requested:

(a)

Please be more specific in identification o

items thai will not be iinspected.

(b)

Please give:

1.

The total estimated man-rem exposure involved in the examination, 2.

The radiation levels at the examination area 3.

Flushing or shielding capabilities which might reduce radiation levels.

4.

A proposal for alternate examination technioues 5.

A discus'sion of the considerations involved in remote examination.

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Similar welds in redundant systems or similar welds in the same systems which can be examined.

The results of preservice inspection and any inservice results for the welds for which the relief is being requested.

A discussion of the consequences if the weld which was not examined, did fail.

Rc, F c. R=NCES:

1.

G.

K.

Rhode (Nj~iPC) to G.

Lear (NRC), letter, December 9,

1976.

2.

D.

P.

Di se (Nt'iPC) to T. A. Ippol ito (NRC), letter, Nay 2, 1980.

3.

"Inservice Inspection Ten-Year Plan Book, Nine Mile Point Unit 1,"

September 17, 1976 (attachment to reference 2) triarch 12, 1982

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