ML18079A945

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Forwards IE Bulletin 79-14,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys
ML18079A945
Person / Time
Site: Salem 
Issue date: 09/07/1979
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Schneider F
Public Service Enterprise Group
References
NUDOCS 7909210263
Download: ML18079A945 (8)
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Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No. 50-272 Public Service Electric and Gas Company ATTN:

Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:

September 7, 1979 The enclosed supplement to Bulletin No. 79-14 is forwarded to you to provide added guidance on the intent of the Bulletin. If you desire additional information regarding this matter, please contact this office.

Enclosures:

1.

Supplement 2 to IE Bulletin No. 79,..14

2.

List of IE Bulletins Issued in Last Six Months Sincerely, cc w/encls:

F. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station

ENCLOSURE l SS INS:

6820 Accession No.: 7908220109 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON*,

D. C.

20555 IE Bulletin No. 79-14 Supplement 2 Date~ September 7, 1979 Page l_of 2 SEISMIC ANALYSIS FOR AS-BUILT SAFETY-RELATED PIPING SYSTEMS Description of Circumstances:

IE Bulletin No. 79-14 was issued on July 2, revised on July 18, and first supplemented on August 15, 1979.

The bulletin requested licensees to take certain actions to verify that seismic analyses are applicable to as-bu_ilt plants.

Supplement 2 provides the following additional_ guidance with regard to implementation of the bulletin requirements:

  • N6nconformances One way of satisfying the requirements of the bulletin is to inspect safety-related piping systems against the specific revisions of drawi_ngs which were used.as input to the seismic analysis. Some architect-~ngineers (A-E) however, are recommending.that their customers inspect these systems against the latest rev is-ions of the. drawings and mark them as necessary to def foe the as-built confi gurati_on. of the. s"ystems *. These.drawings are then returned to the AE Is offtces for compari.son by* the* analyst to the seismic analysis input.

For licensees taking.thJs approach, the seismic analyst will be the person who wi 11 identify 'nonconform~nces.

  • Th_e* ftrst* supplement to the bulletin provided guidance with regard to evaluation of nonconfor~~nces. That guidance is approp~iate for licens~es inspecting*

_11gai_nst later drawings~. The. licensee should assare that he is promptly notified w.flen the AE*identtfi,es a nonconformance~ that the initial engineering judgment ts*coriJpleted tn two days and that the* analytical engineerin"g evalua.tion "is corople.ted in 30" days.* *rr etth.er th_e*engineerfog Judgement or the analytical e_n~ineeri_ng.ev~luation indicate.s that system *opera.bili"ty is in jeopardy, the licensee*i:~ expected to meet theapplicable*techni'cal specification action statement.

... -.... ~.....

Visual *Approximations Some licensees are visually. estimating pipe lengths and other inspection elements:, ~nd have not documented wh_ich_ data h*ave been obtained in that way.

Yisu~l esti.roaticrn.*of dimenstons -ts not encouraged for most measurements; however, where. vtsual esti.m~tes are used~. the.. accuracy.* of estimation must be within tol er-ance reqiJirements. *.further~ in documenting the data, the licensee must specif-icall,y*identtfy those* data that.were visually estimated.

Enclosure l Thermal Insulation IE Bulletin No. 79-14 Supplement 2 Date:

September 7, 1979 Page 2 of 2 In many areas, thermal insulation interferes with inspection of pipe support details, i.e. attachment welds, saddles, support configuration, etc.

In some areas, the presence of thermal insulation may result in unacceptably large uncertainties for determination of the location of pipe supports.

Where thermal insulati.on obstructs inspection of support details, the insulation should be removed for inspection of a minimum of 10% of the obstructed pipe supports in both Item 2 and 3 inspections.

In the Item 3 response, the licensee should include a schedule for inspecting the remaining supports.

Where riecessary to determine the location of pipe supports to an accuracy within.

design tolerances, thermal insulation must be removed.

Clearances For exposed attachments and penetrations, licensees are expected to measure or estimate clearances between piping and supports, integral piping attachments (e.g. lugs and gussets) and supp.orts, and piping and penetratfons. Licensees are not exi:iected fo do any disassembly to measure clearances.

  • *Loose Bolts Loose anchor bolts are not covered by this bulletin, but are covered by IE Bulletin No. 79-02.

Any loose anchor bolts identified during actions taken for this bulletin should be dispositioned under the requitements of Bulletin No. 79-02.

Other loose bolts are to be treated. as nonconformances if they invalidate the seismic analysis;. however, torquing of bolts is not required.

Difficult Access Areas where inspections are required by the Bulletin but are considered impractical evenwith the.reactor shutdown, should be addressed on a case by case basi.s.. 'lriformatioti. concerning the burden. of performing the inspection and the safety conseque.nce of not performing the inspection should be documented by* the 1 ice.nsee * ~nc:! forwarded for staff review~

'Schedule

.Tf1e*sche.dule for the action and reporting requitements. given in the Bulletin as or_t~tn~lly issued remai.ns Lincha,_nged.

ENCLOSURE 2 LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS Bulletin No..78-12B Subject Atypical Weld Material in Reactor Pressure Vessel Welds Date Issued 3/19/79 79-0lA Environmental Qualification* 6/6/79 of Class ]E Equipment (Deficiencies in the Envi-ronmental Qualification of ASCO Solenoid Valves) 79-02 Pipe Support Base Plate 6/21/79 (Rev 1)

Design Using Concrete Expansion Anchor Bolts 79-02 Same Title as 79-02 8/20/79 (Rev 1)

(Rev 1)

(Supplement No. 1) 79-03 Longitudinal Weld*Defects 3/12/79 in ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Company 79-04 Incorrect Weights for 3/30/79 Swing Check Valves Man.ufactured by Vel an Engineeri~g Corporation 79-05 Nuclear Incident at 4/1/79 Three Mile Island IE Bulletin No. 79-14 Supplement 2 Date: September 7, 1979 Page l of 5 Issued To*

All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP Same as 79-02 (Rev l)

All Power Reactor Facilities with an OL or CP All Power Reactor Facilities with an OL or CP All Babcock and Wilcox Power Reactor Facilities with an OL, Except Three Mile Island 1 and 2 (For Action),

and All Other Power Reactor Facilities With an OL or CP (For Information)

r LIST OF IE BULLETINS ISSUED IN LAST SIX MONTHS (CONTINUED)

Bulletin Subject No.79-05A Nuclear Incident at Three Mile Island -

Supplement 79-058 Nuclear Incident at Three Mile Island -

Supplement -

79-06 Review of Operational Errors and System Mis-

. alignments Identified During the Three Mile Incident 79-06A Same Title as 79-06 79-06A Same Title as 79-06 (Revis ion l)

Date Issued 4/5/79 5/21/79 4/11/79 4/14/79 4/18/79 IE Bulletin No. 79-14 Supplement 2 Date:

September 7, 1979 Page 2 of 5 Issued To Same as 79-05 Same as 79-05 All Pressurized Water Power Reactor Facil-ities wjth an OL Except B&W Faciljties (For Action), All Other Power Reactor Facil-ities with an OL or CP (For Information)

All Westinghouse Designed Pressurized Power Reactor Facil-ities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information)

All Westinghouse Designed Pressurized Power Reactor Facil-ities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information)

LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS (CONTINUED}

Bulletin Subject Date Issued.

No~

79-06B Same Title as 79-06 4/14/79 79-05C&06C Nuclear Incident at 7/26/79 Three Mile Island -

Supplement 79-07 Seismic Stress Analysis 4/14/79 of Safety-Related Piping 79-08 Events Relevant to 4/14/79 Boiling Water Power Reactors Identified During Three Mile Island Incident 79-09 Failures of GE Type 4/17/79 AK-2 Type Circuit Breaker in Safety Related Systems 79-10 Requalification Training 5/11/79 Program Sta ti sti cs IE Bulletin No. 79-14 Supplement 2 Date: September 7, 1979 Page 3 of 5 Issued To All Combustion Engineering Designed Pressurized Power Reactor Facilities with an OL (For Action), and All Other Power Reactor Facilities with an OL or CP (For Information)

All PWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL (For Action)~ All Other Power Reactor Facil-ities with an OL or CP (For Information)

All Power Reactor Facilittes with an OL or CP All Power Reactor Facilities with an OL

I LISTING OF IE BULLETINS ISSUED IN LAST SIX MONTHS (CONTINUED)

Bulletin No.

Subject Date Issued 79-11 Faulty Overcurrent Trip 5/22/79 Device in Circuit Breakers for Engineered Safety Systems 79.., 12 Short Period Scrams at 5/31/79 BWR Facilities 79-13 Cracking in Feedwater 6/25/79 Systerri Pipfog 79-13 Cracking in Feedwater (Revision 1) System Piping 79-14 Seismic Analy~is for As-Built Safety Related Piping Systems 79-14 Same Title as 79-14 (Revision 1) 79-14 Same Title as 79-14 (Supplement}

79-15 Deep Draft Pump Defi-ciencies 79-16 Vital Area Access Con-trols 79-17 Pipe Cracks in Stagnant Borated Wa,ter Sys.tems

September 7, 1979 Page 4 of 5 Issued To All Power Reactor Facilities with an OL or CP All GE BWR Facilities with an OL All PWRs with an OL (for Action),

All Other Power Reactor Facilities with an OL or CP (For Information)

All Designated Ap-plicants for OLS All Power Reactor Facilities with an OL or CP

  • Same as 79-14 Same as 79-14 All Power Reactor Facilities with an OL or CP All Holders of and Applicants for Reactor Operating Licenses All PWR Power Reactor Facilities with an OL

Bulletin No.

79-18 79-19 79-20 79-21 79-22 LISTING OF IE BULLETINS ISSUED tN LAST SIX MONTHS {CONTINUED)

Subject

  • Date Issued Audibility Problems
  • 8/7/79 Encountered on Evacuation Packaging Low-Level 8/10/79 Radioactive Waste for Transport and Burial Same Title as 79-19 8/10/79 Temperature Effects on 8/13/79 Level Measurements Possible Leakage of Tubes 9/5/79 of Tritium G~s Used in Timepieces for Luminosity

\\

IE Bulletin No. 79-14 Supplement 2 Date:

September 7, 1979 Page 5 of 5 Issued To All Power Reactor Facilities with an OL All Power and Re-search Reactors with OL, all Fuel Faci-lities (except Uranium Mills), and certain Materials Licensees Certain Materials Licensees All Power Reactor Facilities with an OL or CP Each Licensee who Receives Tubes of Tritium Gas in Timepieces for Luminosity

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