Text

Forwards,For Consideration,First Draft of Program Plan. Comments Should Be Submitted by 820226
	ML20209B283
Person / Time
Site:	Diablo Canyon
Issue date:	02/23/1982
From:	Eisenhut D; Office of Nuclear Reactor Regulation
To:	Crews J, Jordan E, Vollmer R; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation
Shared Package
ML16340C148	List: ML16340C147; ML20209B134; ML20209B144; ML20209B172; ML20209B176; ML20209B206; ML20209B218; ML20209B249; ML20209B270; ML20209B277; ML20209B283; ML20209B298; ML20209B443; ML20209B450; ML20209B492; ML20209B597; ML20209B601; ML20209B605; ML20209B682; ML20209B777; ML20209C156; ML20209C239; ML20209C268; ML20209C274; ML20209C285; ML20209C293; ML20209C318; ML20209C326; ML20209C333; ML20209C442; ML20209C446; ML20209C477; ML20209C533; ML20209C551; ML20209C621; ML20210A699; ML20210A793; ML20210A831; ML20210A898; ML20210A977; ML20210B079; ML20210B125; ML20210B142; ML20210B176; ML20210B198; ML20210B218; ML20210B230; ML20210B246; ML20210B256; ML20210B260; ... further results
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	v • d • e

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/f %q'o, UNITED STATES

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g NUCLEAR REGULATORY COMMISSION g

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.j WASHINGTON, D. C. 20555 t

FEB 2 31982 MEMORANDUM FOR:

R. H. Vollmer, Director, Division of Engineering, NRR J. L. Crews, Director, Division of Resident, Reactor Project & Engineering Programs, RV E. L. Jordan, Director, Division of Engineering &

Quality Assurance, OIE FR0!i:

D. G. Eisenhut, Director, Division of Licensin'g, NRR

SUBJECT:

DIABLO CANYON PROGRAM PLAN Attached for your consideration is a first draft of the Diablo Canyon program plan. The PG&E and staff activities, including the November 19, 1981 order, have been arranged in a computerized action plan to allow a management tracking system to be in effect. Since this is just the

" straw man" of the plan, we expect some modifications will be necessary.

You are requested to provide your comments on the plan to H. Schierling (M/S 128) by C.0.8. Friday, March' 5,1982.

. is a flow chart of the entire program. Attachments 2a and 2b provide details on the tasks required by the 11/19/81 Commission Order. Attachment 3 is an explanation of the computer printout. is a computer printout of the major tasks, while Attachment 5 details both major tasks and subtasks.

If you have any questions on this, please contact H. Schierling on X28423.

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7 D 'r e

. Eise ut, irector Division of Licensing Office of Nuclear Reactor Regulation Attachments:

As stated cc:

H. Denton E. Case R. DeYoung W. Olmstead R. Tedesco F. Miraglia 7

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EXPLANATION OF PRINT 0'JT The printout is a " straw man" of the program plan and substantial revisions /

corrections may be necessary. The details of the task data for the full power requirements will be developed shortly.

Each task / subtask is defined by two 1.ines of data as described below. As an example, refer to tas'k number 0703000 which is completely filled out.

Line 1 Entry Number 1

Task / Subtask number (example: 0702011 = Task number 07 Subtask number 02 of task *07 Subtask number 01 of subtask

0702 Subtask number 1 of subtask

070201 2 defines whether task is a fuel load (FL) cf full power (FP) requirement 3 origin of requirement 4 name of task / subtask 5 status of task / subtask Line 2 Entry Number 1

planned submittal / input date 2 actual submittal / input date (not defined for most tasks as yet) 3 submittal nut @er (only used in the event that several submittals are received on the same date) i

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4

l 4 difference between planned and actual submittal dates (in days) 5 Assi5ned lead division 6 Assigned lead person 7 Division f'rox. which input is to be received 8 Persen from whom input is to be received.

i 9-13 NRC schedu'le 9 Plenned task start date l

10 Actual task start date i

11 Planned task completion date f

1 i

e 12 Actual tesk completion date s

13 Difference between planned and actual task completion dates (days) l l

f The attached senedule plot shows only the fuel load tasks versus date. The task / subtask numbers have been indented to more clearly show task / subtask i

relationships.

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UNITED STATES NUCLEAR REGULATORY COMMISSION
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n WASHINGTON, D. C. 20555 p
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MAR 3 1992 MEMORANDUM FOR: Frank Miraglia, Chief Licensing Branch No. 3 Division of Licensing, NRR FROM:
Kenneth S. Herring Systematic Evaluation Program Branch Divison of Licensing, NRR John R. Fair Engineering & Technical Support Branch Divison of Engineering and Quality Assurance, NRR
~~SUBJECT:~~
DIABLO CANYON SEISMIC VERIFICATION PROGRAM INSPECTIONS - FEBRUARY 22 - 26, 1982 As a part of Region V's ongoing acti.vities to keep abreast of the current Diablo Canyon seismic verification program, we conducted unannounced inspections at the R. L. Cloud offices on February 22 and 23,1982, and at the PG&E offices on February 24, 1982.
In addition, a walk-down cf cer-tain aspects of the Diablo Canyon design was conducted at the plant on February 25 and 26,1982, to gain a better understanding of issues identi-fied during the meetings at the R. L. Cloud and PG&E offices. Our observa-tions and recommendations are discussed below.
R. L. Cloud Inspection
~~1) Piping and Supports The piping analysis procedures, signed on 2/22/82, were reviewed.~~
The procedures were based on criteria presented in Section 8.2 of the Hosgri Report with additional criteria for overlap (NUREG/CR-1980),
decoupling (piping diameter ratio >4) and small diameter piping con-nected to large pipe (either (1) large pipe response in the span where the attachment point is located is greater than 20Hz or (2) the large line displacement <1/16 inch). The procedures did not include the load combination or stress allowable criteria.
Two of the R. L. Cloud employees performing piping analyses were inter-viewed. These employees were familiar with the piping analysis proced-ures and criteria.
~
Approved support evaluation procedures were not available at the time of the inspection. The support frequency calculations were available but they had not been approved at the time of the inspection. The re-sults of these calculations showed 19 of the 20 supports met the PG&E criteria for frequency as reported in the R. L. Cloud progress report dated January 9,1982. Review of the calculations showed that snubber m&
b o
y
,, MAR 3 1982 5
flexibilities had not been included in the computations. Cloud employees stated that these calculations had not been approved and the snubber flexibilities wo0ld be included in the final calcula-tions.
2) Ecuipment Calculation Review The only completed, checked and approved calculation packages in any area were those for the Main Annunciator Cabinet located in the Cable Spreading Room and the Diesel Generator Fuel Oil Priming Tank. Review of these calculations indicated the following.
a) Main Annunciator Cabinet - In the calculation of the cabinet response,1) 12 ga. sheet metal side panels ( 25" x 85") were treated as simple beams without verification of the appropriate-ness of this assumption, 2) angle structural members were treated as simple beams without appropriate consideration..of torsion, and
3) the locations of the centroids of the angles sie're computed er-roneously. The last error was found to be due to an error in the handbook used ft calculations, however, it appeared that insuf-ficient consideration was given to the applicability of handbook formulas and the basic assumptions ingrained in handbook and simple beam formula formulations.
Dr. Cloud agreed that the calcuation should be redone. He further indicated that this calculation, in addition to 3 others, had been performed by EDAC under a previous, since cancelled, subcontract. These other calculations were found to be inappropriate by Cloud personnel and were being redone. The cabinet calculation wcs not checked in as much detail as the other 3 since it indicated that an E01 was to be generated. Therefore, he felt that this was an isolated occurance of an approval of an erroneous calculation.
b) Diesel Fuel Oil Priming Tank - No obvious errors were detected in the review of this calculation. However, insufficient attention was given in the evaluation of the concrete anchor bolts used for the supports. This appeared to be due to the low magnitude of the calculated seismic responses, however, we indicated to Cloud that these should be appropriately evaluated in all future calculations.
Given that an error was found in 1 of the 2 completed equipment calcula-tions reviewed, it is recommended that the NRC staff review additional com-pleted eauipment calculations to determine whether or not this is an isolated case.
In addition, it was observed that procedures for perform-ing the analyses of all items in the Cloud verification effort have not yet been finalized by Cloud.
.,RAR 0 1984 g,
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PG&E Inspection
1) PG8E and Blume Civil Engine'ering Related ' Calculations Several topics related to the calculations performed by the PG&E and Blume Ci_vil Engineering personnel were discussed. These discussions are described below.
a) Containment Polar Crane - Discussions similar to those which took place on January 29, 1982, between Mr. Herring and PG&E and Blume personnel were reported.
Since that first discussion,tPG&E had no new information relative to this issue and indicated that they intended to pursue it further.
(See Trip Report K. Herring to F. Miraglia, February 3,1982.).
b) Containment Internal Structure Response Above Elevation 140' - The steam generator and pressurizer enclosures which extend about 40 feet above the operating deck (el.140') were not modeled in the containment structural model. Therefore, floor spectra at el. 140' were used for the. design of piping and equipment attached above el.140' and coupled to these enclosures. The effects of the enclosure flexibility are be-ing evaluated. They indicated that affected ' items include Main Steam and Containment Spray piping, and the safety and power operated relief 4
valves. The analysis of-the Containment Polar Crane in the parked and locked position (at the tops of the steam generator enclosures) is also.
affected since the flexibility of these enclosures was not considered in Blume's analyses of this crane.
c) Containment Pipeway - This steel frame structure, attached to the containment shell exterior, was initially assumed rigid... It appears that this assumption is not valid and the effects of its flexibility are being investigated.
PG&E indicated that items affected include the Main Steam, Main Feedwater and Auxiliary Feedwater piping, and the Main Steam Isolation Valves.
d) Main Annunciator Cabinet - PG8E is analyzing the cabinet flexibility in light of Cloud's finding that it was not rigid as assumed initially.
They indicated.that their prelimiary calculations were demonstrating that the cabinet was rigid. However, the PG&E personnel performing the anal-yses were not aware of the connection details for the doors, internal member and cabinet supports to substantiate the validity of the assump-tions made in their analyses.
f e) Containment Exhaust Vent Structure Flexibility - Blume initially deter-mined (November,1970) that the exhaust vent had a natural frequency of 50 Hz and notified PG&E of this fact.
In Dece nber,1970, Blume.
determined that the 50 Hz was in error and that the frequency was 2 Hz.
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e However, they never notified PG&E of this change. Hosgri evaluations done by PG&E relied upon the 50 Hz frequency and determined that the vent would remain elastic. ~PG&E stated that with a 2 Hz natural fre-quency, recent evaluations indicate that modification's are required for the vent to remain elastic under the Hosgri criteria and they are evaluating the feasibility of a non-linear analysis to demonstrate acceptability without modification.
f) Annulus Spectra Revisions - Three revisions to the containment annulus spectra have occurred since the initial discovery of the annulus problem. The first accounted for appropriate orientation, and the second accounted for appropriate mass and stiffness di stri-butions. PG&E indicated that the latest revision has been necessitiated by Blume discovering (in a recent internal Blume de-sign audit) that the upper vertical massess of the internal struc-ture in the initial Hosgri analyses inappropriately included such items as the Steam Generator, Reactor and Reactor Cool. ant Pumps.
In addition, the two masses of the internal structure were trans-posed in the recent evaluations.
Given these and previously identified problems relating to the analyses performed by Blume, PG&E stated that they were currently formulating a program to, be instituted by Blume to check the adequacy of Blume's past analyses and to identify appropriate final analyses results. We indicated that we concurred with the need for such a program.
2) PG&E Piping Design and Construction Recent R. L. Cloud progress reports have identified several as-built descrepancies during piping walk-downs. One issue identified was valve operator orientation. Correct measurements of valve operator orien-tations apparently were not made during the IE Bulletin 79-14 walk-downs.
PG&E currently plans to walk-down all piping to record correct valve orientations.
According to PG&E the majority of the as-built dimensional descrepancies identified by Cloud were errors in drafting and not in the analyses.
PG&E stated that the original piping drawings that were marked-up during the field as-built walk-downs were used by the piping analysts. These drawings were then sent to the draf ting department to develop the final i somet ri cs. These drawings were not treated as record drawings and therefore, were not subject to stringent quality control procedures.
PG&E currently plans to upgrade the drawing controls on the piping iso-t.
metric drawings and they also plan to perform a sample of 17 walk-downs to the IEB 79-14 criteria.
This effort will require further NRC review when PG&E corpletes the current evaluations on all open items.
l l
l
" MAR.3 1982 '
4
3) Ongoing PG&E Investigations In addition to the work des'cribed above, PG&E is in the process of instituting strong project management control of the in-house seismic reverification effort. Since PG&E has initiated and is initiating several additional internal programs to address the concerns identified by Cloud and themselves, it is reconrnended that the NRC staff meet with PG&E to discuss the adequacy of these programs and to address the open items identified to date..Special attention should be given to assuring that the resolution of problems is approached in an orderly fashion.
Site Visit Observations On our site visit, we inspected the containment exhaust vent, the steam gen-
~
erator and pressurizer enclosures, and the Main Annunciator Cabinet. Our eb';ervations are presented below.
1) Containment Exhaust Vent From a visual inspection of this structure, it appeared obvious that the natural frequencies _ were substantially lower than the 50 Hz calculated initially by.Blume, and used by PG&E in its Hosgri evaluation of this st ructu re.
2) Steam Generator and Pressurizer Enclosures From a visual inspection of these structures, the potential for further amplification.of motion cbove el.140' appeared obvious, especially con-sidering the connection of the Polar Crane to the steam generator enclo-u res.
~~3) Main Annunciator Panel From a visual inspection of this panel, it was observed that:~~
a) The conception of this cabinet ingrained in the Cloud analyses was more representative of the physical configuration than that ingrained in recent PG&E evaluations, b) The analysis performed recently by PG&E contained several as-sumptions which were not representative of the physical situation.
c) Several loose and missing bolts were obvious.
. jd@. 3 1982
~5 -
e Based upon the above observations and the previous discussions of the problems in these areas, it appears that r.eny of these problems could have been avoided if analysts had been required to walkdo,#n these structures.
.!MPeU8.Gleu!Byo Original signed byj, Kenneth S. Herring Systematic Evaluation Progran Branch Divi.sion of Licensing, NRR
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John R. Fair Engineering & Technical Support Bran'ch Division of Engineering and Quality Assurance, '
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