ML20117M585

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Procedure for Determining Snubber Binding in Five Failed Main Steam Snubbers
ML20117M585
Person / Time
Site: 05000000, Dresden
Issue date: 05/27/1983
From:
SARGENT & LUNDY, INC.
To:
Shared Package
ML20114G054 List:
References
FOIA-84-616 PROC-830527, NUDOCS 8505170133
Download: ML20117M585 (27)
v • d • e


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-CARGENT Q LUNDY

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-ENGINEERO CHICA%O

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h Commonwealth Edison. Company Dresden - Unit 2 Procedure for Determining Snubber Binding in the Five Failed Main Steam Snubbers Purpose

The purpose of'this document is to establish a procedure.for evaluating the five failed anubber designs for possible bind-ing._.The support designs to be considered are sho n on the t

following Sargent & Lundy drawings (Attachment A):

M-564Fn2 M-564 col M-564G-2 M-564G-3 i'

M-564H-1 1

With the aid of a fabricated snubber model, replicas of the five failed. snubbers will be used to duplicate design con-ditions.

Piping expansion movements as measured by the LVDT's (Reference 1) and expected thermal movement calculated by_ computer analysis (P.eference 2) will be imposed on the (L~

five ' snubber replicas to evaluate the designs for physical interference and possible binding.

Test Apparatus The test apparatus is a fabricated. snubber model built to duplicate the five actual design conditions.

Components which make up the snubber assemblies are either fabricated from plastic materials or_are actual components obtained from the Dresden Station Maintenance Department.

The com-l ponents which~make up the fabricated snubber model are as follows:

1)

A fabricated portion of an NPS, Industries pipe L

clamp, No. SPC-14-200, load bolt and ends 2)

An actual Pacific Scientific Forward Adapt'or, No.

1801346 for PSA-10 anubber 3)

A fabricated Pacific Scientific snubber assembly and transition tube kit which has adjustable lengths to p

account for the five different pin-to-pin diuensions.

i 4)

An actual Pacific Scientific. rear end piece taken from a PSA-10 snubber assembly.

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-616 PDR p

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CARGENT Q LUNDY ENGINEERO CNICA40

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5) 'A'-fabricated NPS, Industries rear end bracket, No.

SMRB for a size 10 anubber.

The 'five items described above are assembled on a fabricated stand.

The model stand.is designed to permit translation and rotation of the rear end bracket and on the pipe clamp as shown in' Figure 1.

This_ flexibility serves two purposes.

First, it: allows for an infinite number of snubber orienta-tions which can' occur in the design of supports due to the location of the pipe attachment with" respect to the build-ing structural attachment.

And second, it allows for an in-finite number of possible pipe translations and rotations due to pipe-' thermal expansion and equipment nozzle thermal dis-

. placements.

j[est Procedure

-1)

Select a support design to be tested

'M-564F-2 M-564G-1 M-564G-2 M-564G-3 or

/l M-564H-1.

1 L2)

Position rear end bracket, pipe clamp and snubber assembly.on test stand to duplicate cold position of snubber shown on the appropriate support drawing.

Particular attention must be given to the clamp and rear end bracket alignment, snubber pin-to-pin dimension, and' relative dimension between the rear end bracket and pipe clamp._

3)

Using thermal movements as measured,by the LVDT's (Reference 1) and expec*ted thermal movements calculated by computer analysis (Reference 2), adjust pipe' clamp end on test stand to duplicate these movements.

Partic-ular attention must be given to resolve measured movements

'into appropriate components that are consistent with the test stands flexibility as shown in Figure 1.

Figures 1.through 10 of Attachment "B" were prepared to assist.in implementing the test procedure.

Figures l through 5 show the positions of the rear end bracket,-

pipe clamp and snubber assemblies required to duplicate 1 ~

-the-cold design position for the'five failed supports.

Also shown on Figures 1 through 5 are the expected thermal

. movements calculated by computer analysis (Reference 2)

'for the five supports.

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. Figures 6 through 10 are the cold design positions for the five failed supports with the thermal movements as measured by the LVDT's (Reference 1).

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CARGENTQ LUNDY

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Pcgs 3 of 5 ENCINEERO CHICAGO

4) - Determine if there is any surface-to-surface touching at either pipe clamp and/or rear end bracket of test stand.

Fill out data sheet shown in Figure 2 or take appropriate photographs.

5)

Select one of the remaining support design and repeat Items 2, 3, 4, 5 and 6 until all five supports have been tested.

6)

Reference 1)

" Main Steam Monitoring Procedure," Seven-Day Data Evaluation, Dresden Unit 2, EMD Report dated 5/9/83, File Number EMD-043449.

2)

Sargent & Lundy Stress Reports, Dresden Unit 2:

MS-B EMD File No. 041326 MS-C EMD File No. 041341 MS-D EMD File No. 041333

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Commonws.th Edison on7 First Natitnal Plaza. Chicago, mantis Address Reply to: Post Othee Box 767 p

Chicago. Illinois 60690 June 6, 1983

3). - j 5[h.]

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Mr. James G. Keppler, Regional Administrator T

- Region III r

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U.S. Nuclear Regulatory Commission i _.

j p.2 799 Roosevelt Road

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Glen Ellyn, IL 60137 y[

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Subject:

Dresden Station Unit 2 l

Main Steam Line Snubber Failure NRC Docket No. 50-237-References (a):

8. Rybak letter to J. G. Keppler dated May 13, 1983.

(b):

B. Bybak letter to J. G. Keppler dated May 24, 1983.

(c):

B. Bybak letter to J. G. Keppler dated May 27, 1983.

Dear Mr. Keppler:

In our submittal of May 13th, we committed to provide a plan for s

checking for clamp interferences on the Main Steam Line (MSL) PSA-10 m

snubbers.

This letter provides an overview of that plan.

Per Reference (c), we submitted to the NRC a binding report documenting the results of S&L's investigation to determine i-f. binding was occurring on Dresden 2 MSL snubbers considering the components installed and the design of the installation.

As a result of the study it was determined that in the as designed configuration neither the j

design thermal growth nor the LVDT indicated thermal growth resulted in a binding problem.

Considering the results of this study, then, the next logical step to resolve this issue is to verify the as-installed configu-j ration of the snubber.

This will be performed for the locations of the

)

l five previously failed snubbers.

This information will also be obtained for any other locations where failures are found, if any, during the 62 day snubber inspection.

Also in Reference (c) we committed to provide results and an update of the ongoing thermal growth evaluation.

As stated previously i

Sargent & Lundy is reviewing additional snubber test data.

They are also developing a plan for determining LVDT accuracy for the D-2 test setup.

~

JUN 71883

{

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'J.

G. Keppler June 6, 1983

-This' effort-is still ongoing.

Results are now expected to be available by June 22, 1983.

If there are any additional questions regarding this matter,

.please: contact this office.

Very truly yours, t

B. Rybak Nuclear Licensing Administrator 1m cc: -Resident Inspector - Dresden R. Gilbert - NRR L

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UNITED STATES E \\, )N/e j v.( ( g NUCLEAR REGULATORY COMMISSION

_ {.;

REGION V 1 0,, - g C-1450 MARIA L ANE.SulTE 210

%.f\\#

,o WALNUT CREE K. CALIFORNIA 94596 JUN 201983

Docket No. 50-312 f$'g-L& d Sacramento Municipal Utility District P. O. Box.15830 7D

. </D Sacramento, California. 95813

(/

Attention: -Mr. Ron Rodriguez Executive Director for Nuclear Operations Gentlemen:

Subject:

NRC Inspection of Rancho Seco This-refers to the routine monthly inspection conducted by Messrs. H. Canter

& J. O'Brien of this office between April 30, 1983 and June 8, 1983 of activities authorized by NRC License No. DPR-54 and to the discussion of our findings held-by Messrs. Canter & 0'Brien with Mr. P. Oubre' and other members of your staff a the conclusion of the inspection.

Areas-examined during this inspection are described in the enclosed inspection report. Within.these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with

_ personnel,'and observations by the inspectors.

No items of noncompliance with-NRC requirements were identified within the scope of.this inspection.

In'accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures will be placed in the NRC Public Document Room unless you notify this office,

-by telephone, within ten days of 'the date of this ' letter and submit written application to withhold information contained therein within thirty days of

.the'date of this letter.

Such application must be consistent with the requirements of'2.790(b)(1).

j

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e

^

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~Jull ? 01903

- Sacramento Municipal f.7tility District '

.2 Should.you havE any'q aestions concerning this inspection, we will be glad to discuss them with you.

Sincerely,

' l. N \\\\ k 1 7 3 9 [ ^ Il 1

.D. M. Sternberg, Chiel * '

)

Reactor Projects Branch )

~..

Enclosure:

u..

' Inspection Report I

No. 50-312/83-17 cc w/o enclosure:

L.' G.,.Schwieger, SMUD J-l

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s OFFICE OF INSPECTION AND ENFORCEMENT REGION-V

~~

Report No. 50-312/83 Docket No. 50-312 License No. DPR-54 Safeguards Group Licensee: Sacramento Municipal Utility District

~

P. O. Box 15830'

-Sacramento, California 95813 Facility Name: Rancho Seco Unit 1 i'

. Inspection at: Herald, California (Rancho Seco Site) h24M4 d-/7"h3 4

Inspectors:

c-Ifarvey L. Canthr, SengrpResiddat Inspector Date Signed Onsuph. 4, to-jg 23 John O'Brien, ($ nit Ret.d$tt In/p~ector Date Signed Approved by:

M d'[743 T. Young, Jr., pief Rektgr Projects Section 2, Date Signed Reactor Projects Branch No. 1 Summary:

Inspection between April 30-June 8, 1983 (Report'No. 50-312/83-17)

Areas Inspected:

Inspection during long-term shutdown; maintenance observations;. surveillance observations; TMI modification follow-up;

follow-upi,_on Licensee Event Reports; Review of plant operations, follow-up on Enforcement Items;;fol1ow-up on Regional requests; media contacts and

~

. independent inspection effort. The inspection involved 214 inspector-hours performed by two resident inspectors.

Results: Of the ten areas inspected, no items of noncompliance were identified.

,1 1

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DETAILS 4

1.

Persons Contacted-R. Rodgriguez, Executive Director, Nuclear Operations 1 P. Oubre', Manager of Nuclear Operations 2 D. Blachly, Operations Superintendent E.' Bradley, Supervising Environmental Specialist N. Brock, Electrical /I&C Maintenance Supervisor Q. Coleman,. Mechanical Engineer R.. Colombo, Technical Assistant R. Cordons, Emergency Planner 2 G. Coward,-Maintenance Superintendent D. Cradle, EMD Mechanic

'1,2;S..Crunk, Associate Nuclear Engineer

' 2 D.,Elliott, Senior Quality Assurance Engineer 2 B. Fraser', Electrical Engineer D.;Gardiner, Senior Chemical & Radiation Assistant J.-Hutchensen, Allis-Chalmers Mechanical Engineer J. :Jewett,- Quality Assurance Engineer 1,2 W. Jurkovich, Supervising Resident Construction Engineer.

F. Kellie, Assistant Chem. and Radiation Superintendent IlR. Lawrence, Mechanical Maintenance Supervisor

-1 J. McColligan, Principal Project Engineer 1 B. Mquade, Quality Assurance Engineer 1,2 R.iMiller,-Chemistry / Radiological Superintendent 1,2 T. Perry, On-site Quality Assurance Supervisor J. Price, Surveillance Test Coordinator

'2 S. Redeker,-S.T.A. Supervisor S. Rutter, Quality Assurance Director L. Schwieger, Quality Assurance Director B. Spencer, Shift Supervisor T.-Tucker, Planner / Scheduler J.'Uhl, Mechanical Engineer 1 B. White, Associate Electrical Engineer D. Whitney, Engineering and Quality Control Superintendent B. Wichert, Plant Mechanical Engineer W. Wilson, Senior Chemical & Radiation Assistant The inspectors also talked with interviewed several other licensee.

employees, including members of the engineering, maintenance, operations and quality assurance (QA) organizations.

I' Denotes those attending the Exit Interview on May 18, 1983.

2 Denotes those attending the Exit Interview on June 1, 1983.

_ =-

e 2

2.

Inspection During Long Term Shutdown During the' report period, the inspectors observed control room operations,. reviewed applicable logs, and_ conducted discussions with control _ room operators. The inspectors verified surveillance tests required during the shutdown were accomplished, reviewed tagout records, and_ verified applicability of containment integrity. Tours of Auxiliary Building and Reactor. Building accessible areas, including exterior areas were made to assess equipment conditions, plant conditions, radiological controls, safety.and adherenceoto regulatory requirements and to verify-that maintenance requests had been initiated for equipment in_need of maintenance. The inspectors observed plant housekeeping / cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The inspectors by observation and direct. interview verifieid that the physical security plan was being implemented in accordance with the station. security plan. The inspectors reviewed the licensee's jumper / bypass controls to verify there were no conflicts with technical specifications and verified the implementation of radio' active waste system controls. The inspectors witnessed portions of the, radioactive waste systems controls associated with radwaste shipments and barreling.

The plant has been in a major outage status during this report period.

The critical path items which must be completed on schedule in order to meet a July 31, 1983 on-line date include work on Hydrogen Monitors, the

' Interim Data Aquisition and Display software, the post Accident Sampling System, Nuclear Service Electrical Building fire protection and electrical systems, Main Steam Reheaters, Acid / Caustic modifications, and turbine repairs.

A management change was announced during this report period in that Mr. Pierre Oubre' has moved from Plant Superintendent to the Manager of Nuclear Operations position, previously held by Mr. Ron Rodriguez, the new Executive Director, Nuclear. The job announcement for the new Plant Superintendent closes on June 15, 1983. Also, the Plant Nuclear Engineer resigned during this period and finally, the Operations Superintendent announced his resignation, effective in August, 1983.

By the end of this report period all thermal shield and barrel bolts were in place. NRR has been kept informed of the bolt work, but has not closed out the issue.

No items of-noncompliance or deviations were identified.

3.

Maintenance Observations The inspectors observed portions of the maintenance activities listed below and verified that work was accomplished in accordance with approved procedures, that work was accomplished by qualified personnel, that provisions for stationing a fire watch to oversee activities involving welding and open flame were complied with and that LCO requriements were met during repair.

y 3

i

. Containment isolation valves for the' Reactor Building Purge system a.

(See comments Paragraph 6).

b.

"A" Fuel ' transfer tube track repair.

Letdown heat exchanger installation.

c.

d.

Thermal shield and core barrel bolt installation and torquing

= opera tions.

e.

Diesel Generator: The inspector witnessed major-tune-up work on the "A" diesel. An Electromotive Division (GE) representative was performing the work. He appeared to have extensive knowledge about the equipment he was maintaining.

No items of noncompliance or deviations were identified.

4.

Surveillance Observations t

The inspectors observed portions of the below listed surveillance testing to verify that the tests were covered by properly approved

. procedures; that the procedures used were consistent with technical specification requirements; that minimum crew requirements were met; that test prerequisites were completed; that special test equipment was calibrated and in service; and, that the test results were adequate, SP201.03B - (Motor Driven) P-440 vire pump operational test.

a.

b.

SP206.03A "A" Diesel generator surveillance test.

SP212.01D - Sample / Analysis of breathing air.

c.

i.((SP'2biddB,,'Saf$ty systsm Hydraulic Snubber' Surveillance tests

~

~

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(partial).

' ~

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~

SP205.02 - Local Component leak rate test of Reactor Building purge e.

valves.

No items of noncompliance or deviations were identified.

5.

Three Mile Island Modification Followup Previous inspection reports document various actions taken by the SMUD to comply with-NUREG-0737, TMI Action Plan requirements.

This paragraph documents further activities performed by the inspectors in support of the NRC verification activities, a

i

7 I

i' 4

a.,

a.

~NUREG-0737J--Item I.A.1.3.2.Ai ' Minimum Shift Crew'(Closed)

~

~

^

~ Generic Idtter 82-33 states in effect that having four licensed a

operators per shif t is to be' thought of as guidance. The licens'ee.

is still pursuing 6-4. licensed operator crews _ by June,1985, but the inspectors. review of this item is CLOSED because of the generic letter statement. This item could be reviewed in the future as the cNRC_ inspection requirements dictate, b.

NUREG-0737 - Item I.C.1: ' Short-term Accident & Procedures Review (0 pen)

T Paragraph 2.B and 3.B of this item are to be implemented as part of the ATOG (Abnormal Transient Operator Guidelines) procedure-

~

modifications. The effort is currently scheduled for implementation y

during the 'next refueling outage in 1985, so this review will be delayed until that time.

~

c.

NUREG-0737:

Item II.D.3.1 - Direct Indications'of Valve Positions

[

-(Closed)

All actions necessary'to meet the requirements for this issue are now complete. The charge converter and cable problems mentioned in reports 50-312/81-12, 80-29, and 80-23 have been solved with the running of new cables in the Reactor Building and the movement of the charge converter to the "TMI" panel in the Computer Room. This item is CLOSED.

No-items of noncompliance or deviations were disclosed.

?6. -

Licensee Event Report Follow-up (LER)

The resident ' inspectors performed an examination of the following LERs to ascertain whether additional inspection effort or other IE response is-warranted, whether.correcrive action discussed in the licensee's report' appears appropriate, and whether the information reported to the NRC i

appea'rs.to satisfy reporting requirements.

In addition, the inspectors attempted to ascertain whether these events involved continued operation

.in violation of regulatory requirements or license conditions.

a.

.The LER's listed below appear to meet the above criteria and require

.no.further followup at this time.

(1) 81-02-LO: Replacement of the "A" Letdown Cooler (Closed)

A new-letdown cooler, to supplement the existing system was

. designed and put in place during the last outage.

(Start of Cycle 5)'The inspector witnessed the final tie into-the existing system and reviewed the associated welding and maintenance procedures.

This item is' CLOSED.

i i

5 (2) 83-07-LO:

"D" RPS Underpower Relay Failure for "C Reactor Coolant Pump (Closed)

See discussion under LER 83-17-LO.

This item is CLOSED.

(3) 83-13-LO: Reactor Building Purge Filter Failure (Closed)

The inspector reviewed the procurement documents and completed surveillance tests and verified the licensee took the appropriate corrective action prior to refueling operations.

This item is CLOSED.

'(4) 83-14-TO: Failed Local Leak Rate Tests of the Reactor Building Purge Valves (Closed)

This item was addressed in Paragraphs 3 and 12 of Region V inspection Report No. 50-312/83-10.

Since that time, the licensee has been visited by an Allis-Chalmers representative'. He verified that the licensee had taken i

proper corrective action, and recommended that increased preventative maintenance be performed on the air operating cylinders. The resident inspector interviewed the representative and found him to be experienced and knowledgeable concerning operations, and maintenance of these valves. The vendor representative was also aware of the NRC concerns dealing with the operation of the valves during post LOCA conditions.

The Resident Inspectors have reviewed the preventative maintenance schedule, machinery history and surveillance history of these valves.

The licensee has increased the priority of the preventive maintenance of the air operators, and had committed to increasing the frequency of the surveillance testing.

This item is CLOSED.

(5); 83-12-LO: Missed Snubber Surveillance Test, and.83-16-LO-

- Snubber Surveillance Test. Failures -(Closed)

The licensee is presently performing an extensive inspection and maintenance program for the safety-related hydraulic snubber systems.

The Bergen-Patterson vendor has provided an improved valve body and poppet seat, and the licensee is reworking the affected snubbers. The Resident Inspectors have witnessed a portion of the testing of the snubbers, and have reviewed procurement documents, maintenance procedures and the surveillance test documents (SP201.10B). The inspectors have verified the licensee has taken adequate corrective actio~n for those snubbers that have failed.

This item is CLOSED.

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.b.

. The LER's listed below do not meet the above criteria and require further followup action by the licensee.

- (1) 21-L2: Feedwater Nozzle Replacement (Open)

The licensee has decided to continue through Cycle 6 wit'h the same feedwater nozzles as last cycle. Replacement has been delayed due to procurement delays, but the licensee intends to replace'the nozzles during the next cycle's refueling outage.

The_ pre'ent Preventative Maintenance program will be used to s

maintain the_ quality of the in place nozzles. The followup-to this report will remain OPEN pending modification of the current nozzles.

(2) 83-17-LO: Failure of Phase Balance and Underpower Relays (0 pen)

The licensee's Nuclear Engineering department has a person

-assigned.to look into redesign or replacement of the relays.

This _ work is receiving a' low priority due to the current refueling outage effects on resources. A licensee

-representative stated that these relays are "one-of-a-kind" and a fair amount of engineering may be necessary for replacement. This. representative stated that a priority will be set after the current' refueling outage to followup possible redesign or other corrective action.

In the meantime, the licensee is pursing a method to better test the " Auxiliary Feed = Pump start on loss of Reactor Coolant Pump" circuitry (Technical. Specification 48a in Table 4.1-1).

This circuitry depends on the proper operation of the aforementioned relays. The_ circuit cannot be tested at power, so one option.of the licensee is considering is to incorporate' the test into Surveillance Procedure SP210.01F,

" Cold Shutdown Auxiliary Feedwater Pump Flow Test and Check Valve Full Stroke Test."

If that cannot be arranged, they will write a new Surveil]+.nce Procedure to cover the test. An engineer. started work on these-options on June 6, 1983.

Until-further. action is completed by the licensee this item will remain OPEN.

No items of noncompliance or deviations were identified.

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7.

' Review of Plant Operations The inspector attended, as an observer, a Plant Review Committee (PRC) meeting on May 26, 1983. The membership and meeting frequency met technical specification 6.5.1 requirements. The subject of the meeting was whether or not a problem found on Woodward Governors (EG-B13C) was to be reported as a Part 21 report. The PRC decided that the Quality Assurance organization should report it via Part 21.

The inspector verified that a Part 21 Report was issued on May 27, 1983.

The problem is a possible generic one. The " pointer dise" behind the

" speed setting adjustment control knob" can contact the " dial plate" and cause the diesel to " hang-up" at some speed less than full speed during a diesel start sequence.

This can occur because the pointer disc and dial plate are in the same plane. This prob'em has occurred twice at Rancho Seco.

The first occurence in 1981 was due to improper maintenance techniques.

At that time, adequate corrective action was taken, but the generic aspects were not pursued by the licensee.

While performing a surveillance on a diesel generator with a newly overhauled EG-B13C governor in May,1983, the operators noted that the diesel speed hung-up at about 650 rpm. Upon investigation it was determined that the clearnace was too small between the pointer disc and dial plate.

For corrective action, the licensee machined 1/16 inch off the pointer disc, just as they did after the 1981 event. Retests were satisfactory on all three EG-B13C governors onsite. Also, as mentioned above, the licensee submitted a Part 21 Report and informed the industry of the problem via NOTEPAD, a computer operated industry-wide information system.

No items of noncompliance or deviaitons were identified.

8.

Follow-up on Items of Noncompliauce The inspectors ascertained that the licensees responses for the following items of noncompliance are in conformance with regulatory requirements and that corrective actions are complete.

In this inspection effort, particular emphasis has been placed in the examination of the measures taken to correct the item and avoid further items of noncompliance.

The corrective action should also have been taken in a timely manner. For the items listed below, the licensee's responses are satisfactory, such that the inspector's review is CLOSED.

i a.

Items 82-08-01:

Civil Penalty for Two Level III Violations on l

Safety Related Components Inoperability (Closed)

It is noted tbat during the current refueling outage, the white indicating lights were installed to indicate the physical status of the d-c charging springs on important breakers. Therefore, the corrective actions described in letters to the NRC dated July 12,

-1982; August 31, 1982, Spetember 3, 1982; November 23, 1982; November 29, 1982; December 17, 1982; and February 18, 1983 satisfy the criteria mentioned above.

This item is Closed.

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t-Logging'of-Events (Closed)

Eb.

' Item.82-38-01i

-The li'censee's response. dated December 15, 1982-ad'equately

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addresses corrective action. The corrective actions have been

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1 verified as complete. :This review is CLOSED.

9.-

. Follow-up on Regional Requests p

Duringzthe, inspection' period, pe'rsonnel from the Region V office of the

-NRC in-Walnut. Creek,. California, requested.information from the Resident

' Inspectors regarding1the operation and maintenance of the Rancho Seco:

power' plant.

Information'was obtained and transmitted to the Region V concerning:

a.

Respiratory protection issues.

-b.

Coalinga Earthquake:. The May 4,'1983 earthquake was felt in the Control Room.'.The plant was shutdown.and the fuel was in the. spent 4

fuel pool at the time of the quake..The seismic sensors which

'tb irange -from a' horizonatal deflection of.005g to.25g were not tripped due'to the earthquake. No plant problems developed as a result..

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c.

Special Report 83-01.

-d.

-Core Barrel Bolt replacements.

e.

LEmergency planning.

f.

Welder-qualifications.

g.

-Welding quality.

h.

Drug usuageconsite.

C" i._. Licensee-Event Reports 83-07 and'83-1,7 (See: Paragraph 6)

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Spent Fuel 1 Pool' Leakage: l Leakage through the concrete walls of the

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. Spent' Fuel Pool occurred thisl month. The spent fuel ~ pool ' liner.

-leakage-collection system normally, drains to the Reactor Coolant.

-System Drain Tank (RCDT). The amount of. leakage is not easily quantifiable.- The licensee has: stated.to the inspector that the spent fuel pool liner-has,been known to leak since about 1970 or 1971, prior to plant licensing. The inspector asked the licensee-

during,the May. 18, 1983 exit for information on past leakage,
present leakage, past reports and/or past information on this-problem such that a determination of the seriousness of the leakage can-be determined. ;The' licensee stated that every time the collection system drain-line to the RCDT has been secured over'the
years, borated water has leaked,through. spent fuel pool welds and

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backed up beteween the spent fuel pool stainless steel liner and the concrete support structure.

This acidic water then leaks through construction joints in the concrete and out of the west and east walls to the environment.

The leakage through the walls appears as wetted concrete. A white Boron crystal residue forms. On the west wall, the leakage appears on the grade level of the turbine building, just north of the diesel rooms.

The licensee covered this area with sheet plastic so that personnel would not rub against the boron cyrstals.

The contamination was at a maximum of 2000 dpm.

The leakage appears more extensive on the east side of the building.

This leakage was not covered with plastic because the east side of the building is in a radiologically controlled area or is not easily accessible.

The contamination levels on this side were also about 2000 dpm and not a serious radiological problem.

The licensee will take some corrective action on this issue.

They will:

1.

Pursue diverting leaked water to some other collection system in the future, rather than allow the water to back up in the annulus.

2.

Pursue past documentation of the problem in an attempt to address the USAR discussion of the spent fuel pool liner being Icak-tight.

It is possible that a safety analysis of this problem has been completed which mitigates the problem.

3.

Install a flow meter in the drain line to the RCDT so that the amount of leakage can be quantified and increases in leakage can be detected.

(ECN 3196) 4.

As part of the spent fuel pool re-racking which will commence in October, 1983, the licensee will inspect 100% of all spent fuel pool welds.

Leaks will be patched.

The intent of these corrective actions is to reduce the physical and/or chemical stress on the re-inforcement bar inside the concrete walls and the walls themselves.

action on the above commitments.This item will remain an Unresolved Item pending (83-17-01).

i No items of noncompliance or deviations were identified.

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~10.

Media Contacts During the months of May and June, 1983, the inspectors communicated with the following organizations and/or persons on items of interest with respect to Rancho Seco operations:

Channel 3 - Mr. Tom DuHain a.

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.b.

Channel 4 - San Francisco, Mr. Don Fields Sacramento Bee - Mr. Ted Bell c.

d.

San Francisco Examiner - Mr. Fran Ortiz

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Sacramento Bee - Mr. Ted Bell c.

d.

San Francisco Examiner - Mr. Fran Ortiz San Francisco Examiner - Mr. Tim Reiterman e.

11.

Independent Inspection Effort Discussions were held between the Resident Inspectors and operations, security and maintenance personnel in an attempt to better understand These problems they may have which are related to nuclear safety.

discussions will continue as a standard practice.

On numerous occasions, during the inspection period, the Resident Inspectors attended shutdown status meetings. These meetings are held by the Plant Management to provide all disciplines onsite with an update on the plant status and ongoing maintenance work.

In addition to the above, independent inspection effort was performed on the following items:

Core support assembly inspection (re:

ISI and the search for HPI a.

thermal sleeve parts).

Nuclear Service Electric Building and Diesel Building construction.

b.

Management controls of turbine deck work.

c.

d.

Security computer problems and modifications.

Hot License Training. (Attended a lecture on thermodynamics),

i e.

f.

Item 80-23-02 on Safety Valve and Power Operated Relief Valve indication in the control room is CLOSED.

Corrective action is adequate. See THI Modification Section of this report under NUREG-0737 item II.D.3.1.

g.

Item 82-04-01 on High Pressure Injection and Make-up Pump Lube Oil Cooler replacement is CLOSED. Stainless steel coolers are onsite and will be' installed prior to startup from the current refueling outage.

h.

Item 82-25-01 on implementation of a computer operated software training records system will remain OPEN until a secheduled implementation in September, 1983. The delay from July, 1983, is due to the priority set on this program by plant management.

Instrument and Control personnel are being utilized on higher priority items and hence, the work on this sytem has been delayed.

This computer software system is also being used to upgrade the plant security system. The hardware system is installed.

No items of noncompliance or deviations were identified.

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12 '. Unresolved Items k

-Unresolve'd' items are matt'ers about which more information is required in order to ascertain whether they are acceptable items, items of E

noncompliance, or deviations. An unresolved item disclosed during the inspection is discussed in Paragraph 9.

13. Exit' Interview

~ The inspector met with licensee ' representatives (denoted in Paragraph 1)

- throughout the month and at the conclusion of the inspection of June 1, 1983, and summarized the scope and findings of the inspection activities.

~The inspector informed.the licensee that other than Three Mile' Island.

related commitments,.the only NRR'related " hold items" for startup deal with the missing thermal sleeve from the Make-Up nozzle and the status of the~ core barrel bolt replacement work.

The licensee acknowledged the inspectors findings.

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