ML20011A766

USNRC IE Bulletin 79-14 Final Rept.

ML20011A766
Person / Time
Site:	Three Mile Island
Issue date:	10/01/1981
From:	GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
To:
Shared Package
ML20011A765	List: ML20011A764 ML20011A766 ML20011A767
References
003, 3, IEB-79-14, NUDOCS 8111030098
Download: ML20011A766 (8)

Text

-- - .

1 THREE MILE ISLAND NUCIEAR GEERATING STATION UNIT - 1 DOCKET 10. 50-289 USNRC I.E. BULLETIN No. 79-14 FINAL REPORT

'IOPICAL REPORP # 003 PROJECT ID: 5020-G5301 Gilbert Associates, Inc. - AUTHORS

! AUTHOR '

~ '

f/hf

• DATE APPROVALS:

1

^

f b

_ i/ l N MANAGER / DATE

~

b10-71

. -n -

cu s ws.a VICE PRESIDDif DATE TECHNICAL FUNCTIONS (SIGNIFICAfTf IMPACT REVIEW) 8111030098 811023 PDR 0 ADOCK 05000289 PDR

i s, e TABLE OF C0ffIDTTS ITH4 PAGE I INIRODUCTION 1 II ACTION ITH4S AND RESPONSES 1-6 III muerES 6 I

l l

t

(

e l

l l

.. ._ )

m .__ _ c,' .

s. t .

Page'1'of 6 .

I. INI'RODUCI' ION

'Ihe following is a sumary response for Metropolitan Edison Ccripany's Three Mile Islard Nuclear Station, Unit 1, to each Action Item of the USNBC I E Bulletin 79-14. Attached is '4DR 'IMI-194, Rev. 2, which is the final' report that explants our detailed compliance to the requirements of ,

I3 Bulletin 79-14. 'Ihis supercedes our previous response dated 10-13-80 transmitted via letter TIL 518. TDR 'IMI-194, Rev. 2, will hereafter be called Reference 1.

II. ACTION ITEMS AND RESPONSES BUIIEI'IN ' ACTION ITEM 1

" Identify inspection elements to be'used in verifying that the seismic analysis input information confoms to the actual configuration of safety-related systems. For each safety-related system, submit a list of design documents, including title, identification number, revision, and date,'which were sources of input information for the seismic analyses. Also submit a .

description of the seismic analysis input infomation which'is contained in each document. Identify systems or portions of systems which are planned to be inspected druing each sequential inspection identified in Items 2 and 3 Submit all of this information within 30 days of the date of this bulletin".

SUbt4ARY RESPONSB 'IO ACTION ITEM 1 A list of dtEign doctments, with their contents, and a listing of inspection elements was initially transmitted via CQL 1092 dated 8-24-79 A detailed description of the elements of inspection and their inspection methods, systems or portions of syatems inspcated and a tabulation of associated .

design documents with a description of their contents have been assembled ,

and documented in Reference 1.

BULLEI'IN ACTION ITEM 2 "For portions of systems which are normally accessible, . inspect one system in each set of redundant systems and all nonredundant systems for confomance to the seismic analysis input infomation -

set forth in design documents".

". . . . ..subm t a description of the results of this inspection".

i

Q .

Page 2 of 6

SUMMARY

RESPON3E 'IO ACTION ITE*i 2 Insp6cuions have been completed on all-systems ca portions of systems subject to the Bulletin requirements. The ircpections were conducted -

utilizing an approved inspection procedure, written specifically to include elements of inspection required by the Bulletin. Inspections were conducted utilizing measurement techniques appropriate for the task.

Nonconfomances found between the physical installation of the piping and rupports and the design documcuts were noted on. inspection reports and forwarded for Engineering evaluation. Inspection findings are explained, and tabulated by *.he analysis identification number in Reference 1.

Details of inspecticns which were affected by adverse conditions such as radiation, accessibility or pipe insulation are listed on a case-by-case basis in Reference 1. An explanation of each situation along with justification for,same is provided.

BULIETIN ACTION ITEM 3 ,

"In accordance'with Item 2, inspect all other nomally accessible

~

safety-related systems and all normally inaccessible safety-related systems".

SUMMARY

RESPONSE 'IO ACTION ITEM 3 ,

The response to this Bulletin Requirement is the same as tliat presented under Sumary Response to Action Item 2 above. Inspections are considered to have been calplet~ed as requi"ed by both Action Items 2 and 3 No further' inspections are planned.

BULETIN ACTION ITB414A If nonconformances are identified:

" Evaluate the effect of the nonconformance upon system operability under specified earthquake loadings and comply with applicable action statements in your technical specifications including prompt reporting".

f~

s .. .

Tage 3 of 6- j t

SGNARY RESPONSE 'IO ACI' ION I'IE4 A Nonconformances, found during inspections, wem submitted for Engineering Evaluation. If the mnconformances affecced tla original Seismic Analysis, a piping reanalysis was_ conducted. If. the nonconfomances 'did not affect -

the original piping analysis the pipe support hardere was evaluated for c T innce with tha design criteria. In either case, the pipe supports were

evaluated for load carrying ability considering specific nonconfomances.

'ihe folloiwng approach has been adopted for pipe support evaluations, due to the present safe shutdown condition of Three Mile Island Nuclear Station, Unit 1. Any pipe supports, on Seismic Category I piping system, with pipe support steel stmssed above 1.6 (1} times AISC(78) code allowables, or pipe support hardware with a factor of safety les i;han 2.5 based on reconmended

loads published in the vendors' catalogs, or concrete expansion anchor having a factor of safety less than 2.0, have been redesigned and will be repaired .

prior to matart. In accordance with the Technical Specifications,_a generic Licensee Event Report (LER) #Sl-007-99X-0, dated July 17, 1981 has been filed with the USNBC.

(1) USNRC Standard Review Plan 3.8.3 and 3.8.4.

BntmTN ACI' ION ITH4 4B

" Submit an evaluation of identified nonconformances on the validity of piping and support analyses as described in the Final' Safety Analysis Report (FSAR) cr other NRC approved documents.-

Where you determine-that reanalysis is necessary, submit your schedule for: (1) completing the reanalysis, (ii) cocparisons of the msults to FSAR or_ other NRC approved acceptance criteria, and (iii) submitting descriptions of the results -of reanalysis"..

B SUf+%RY RESPOfLSE 'IO ACTION I'IEM_4_B, Evaluations of identified nonconformance and subsequent seismic reanalysis have been completed and the results of the reanalysis are presented in Appendix IIIA of Reference 1. Comparison of these results to the adequacy of the existing pipe supports is tabulated in Appendix IIIB of Reference 1.

I

. Page 4;of 6 BULETIN ACTION I'IE14C "In lieu of B, submit a schedule for corm cting rienconfa ming systems so that they conform to the design documents. Also submit ,

a description of tha work required to establish conformance".

SUFNARY RESPONSE 'IO ACTION ITEM 4C Ir. conjuncti'>n with the manalysia af Seismic Category I Piping Systems, subject to the Bulletin requirements, pipe st'.pport repair / rework / additions are required. 'Ihis action is required to either correct a nonconfomance found during inspections or to implement the output of the pipe reanalysis.

'Ihe constr'.tction plan for this. work has been divided into two phases:

Fnase 1: Pipe support steel stressed above 1.6 times the code allo ebles, concrete expansion anchors having a factor of" safety less than 2.0 -

and pipe support hartlware having a factor of safety. less than 2.5 will be redesigned and repaired prior to restart.

Phase 2: Pipe support steel stressed above the allo mble stress limit but ,

less than 1,6 times the code allowable, concrete expansion anchors having a factor of safety between 2.0 and 5 0, and pipe cupport-

! hardware having a factor of safety between 2 5 and 5.0, will be repPired after restart.

i A detailed breakdown of support repair / rework and new support design due to i

! .I.E.Bulletin 79-14 can be seen in Appendix III of Reference 1.-

l Examples of pipe support repair / rework are as 'follows:

0 Add additional structural bracing to existing support l

l 1

i e

~ ~ , , - - , .-, , , , .,-7 . -.-, .,-. . . - ~r ,e,., .,a

Page 5 of 6 0 Add shear lugs to pipe to resist axial pipe loading o -Replace existing spring or snubber with different size

~0 Reset existing variable support 0 Revise Ibnction of existing support -(i.e., tension rod to sway strut) 0 ' Add bracing to existing U-Bolt type support to resist side loading on U-tolt.

O Ravise baseplate and concrete expansion anchors in conjunction with the requirements of I.E.Bulletin 79-02.

BULIETIN ACTION ITEM 4D

" Revise documents to reflect'the as-built conditions in plant, and describe measures which are in effect which provide assurance that futum modifications of piping systems, including their supports, will be reflected in a timelf manner in design doctments and the seismic analysis".

SUMMARY

RESPOIEE '1D ACTION ITEM 4D ,,

Documents have.been prepared to reflect the "as installed" condition of all piping and pipe supports subject to the Bulletin requirements. These documents are the result of updated design control procedures which provides for review and acqui'... ion of as-built data after field modifications have been ccrnpleted. These procedures are to be used to monitor and to control future modifications as required. A sumery of the procedures is as follows:

Drawings are prepared to depict a proposed modification. The rodification is initiated, monitored and cornpleted using approved QA procec'ms. 'Ihe corpleted installation is then inspected by Quality Control for ,onfomity to drawings and specifications. When the insullation is approved by QC, the drawings, ine'ciding approved design changes to these drawings, provide the "as-built" documentation.

I- _ 1

~sl*

• Page 6 of 6 III. r aux;X:ES

1. Metropolitan Edison, I.E.Bulletin 79-14 Rev 2 Response, TDR 'HC-194 dated August 31, 1981.

2. Metropolitan Edison, I.E.Bulletin 79-14 Initial Response - August 24, 1979 3 AISC "Specificaticns for the Design, Fabrication and Erection of Structural Steel for Buildings," November 1, 1978.

4. U. S. Nuclear Regulatory Cormiission, Standard Review Plan, Section 3.8.3, " Concrete and Steel Internal structures of Steel or Concrete Containments", NUREG-75/087, dated 11/24/75.

U.S. Nuclear Regulatory Comission, Standard Review Plan, Section.3.8.4, "other Seismic Category I Structum", NUREG-75/087, ,

dated n/24/75 5 Grinnell, " Pipe Hangers and Supports", Catalog PH-69, Grinnell' Car:pany,-

Inc., Providence, R.I., 1969 Grinnell, " Pipe Hangers", Catalog PH-72, Grinnell Corpor' tion, Providence, R. I., 1972.

Basic Engineers, " Pipe Hangers", BE-168, BE Division of NAVC0 - National Valve and Manufacturing Co., Pittsburgh, Pa., no date.

6. Metropolitan Edison, I.E.Bulletin 79-02 Response July 22, 1981.

.