IR 05000424/1987009

From kanterella
Jump to navigation Jump to search
Insp Rept 50-424/87-09 on 870115-16 & 0202-03.No Violations or Deviations Noted.Major Areas Inspected:Preoperational Insp of Liquid & Gaseous Radwaste Sys,Liquid & Gaseous Effluent Monitoring & NUREG-0737 Items
ML20210T851
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/11/1987
From: Kahle J, Stoddart P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20210T802 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-TM 50-424-87-09, 50-424-87-9, NUDOCS 8702180324
Download: ML20210T851 (9)


Text

~

'

.

,

,

,

,--

s m E,870 UNITED STATES

]

a

,

,

o NUCLEAR REGULATORY COMMISSION

~,

[-

REGION 11 n

$

,j_

101 MARIETTA STREET,N.W.

~*

ATLANTA, GEORGI A 30323

'+9.....,d

.

FEB 121987 Report No.: 50-424/87-09 Licensee: Georgia Power Company P. O. Box 4545 Atlanta, GA 30302 Docket No.: 50-424-License No.: CPPR-108 Facility Name: Vogtle 1 Inspection Conducted: - January 15-16, and February 2-3, 1987 Inspe tor:

[6]d Me//~2 P/ toddart Date Signed

'

Approved b)

O(

k

&//, // 7 J.

hle, Section Chief

.

.

Date Signed D

sion of Radiation Safety and Safeguards

,

SUMMARY Scope:

This routine announced inspection involved. the areas of preoperational inspection of liquid and gaseous radwaste systems, liquid and gaseous effluent monitoring, and NUREG-0737 items.

Results: No violations or deviati.ons were identified, s.

.

.

A '

'

870218 h h 24 PDR A

PDR

.

f

.

,

- _,.

'

.

,

-

.

REPORT DETAILS 1.

Persons Contacted

"

Licensee Employees

  • C. W. Hayes, Quality Assurance Manager
  • C. Belflower, QA Site Manager
  • L. Zehner, Regulatory Specialist
      • D. Hallman, Plant Chemist
  • P. Burnwinkel, HVAC Engineer J. Pappas, Startup Engineer P. Jackson, PASS Engineer
      • R. Hand, Process and Effluent Radiation Monitoring System Engineer M. Kurzman, GPC Training Center M. Fitzpatrick, GPC Training Center
    • W. Gabbard, Regulatory Specialist
    • K. Whitt, Generation Engineer
    • S. Ewald, Manager, Radiological Support
    • T. Greene, Plant Manager
    • J. Daniel, Radwaste Superviror Nuclear Regulatory Commission
  • J. Rogge, Senior Resident Inspector - Operations H. Livermore, Senior Resident Inspector - Construction R. Schepens, Resident Inspector - Operations
  • Attended exit interview on January 16, 1987
    • Attended exit interview on February 3,1987

-

      • Attended exit interviews January 16 and February 3,1987 2.

Exit Interview The inspection scope and findings were summarized on January 16, and February 3,1987, with those persons indicated in Paragraph 1 abcve.

The inspector described the areas examined and discussed in detail the inspection findings listed below. No dissenting comments were received from the licensee. Ten open items from previnus inspections were closed, leaving eight items remaining as incomplete.

These were primarily tracking items which had been delayed or postponed until after fuel load but were scheduled to be completed prior to full ' power operation.

The post-accident sampling system (PASS-II.B.3) and high-range effluent monitoring and sampling systems (II.F.1) were fully checked out and found to be acceptable for full power operation.

However, the PASS will be evaluated after the plant has been at full power for at least 30 continuous days.

The licensee did not identify as proprietary any of the material provided to or reviewed by the inspector during this inspectio __

_

__

__. __.

_.

_

_,_ _.

.-

_

___

__

__

_

,

,.

[

-

.

.

i.

3.

' Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.

4.-

Process and Effluent Radiological Monitoring and Sampling System (PERMSS)

(84523,84524)

Preoperational testing. of the process and effluent radiological monitoring system was completed on. January 11,-1987, and was reviewed by the inspector on January 15, 1987.

Preoperational Procedure.1-3SD-01 covered. the engineering safety feature (ESF) portion of the PERMSS and 1-3SD-02 covered

the non-ESF portion. The procedures appeared to be 100% complete.

'

1 The inspector reviewed calibration.. procedures and-records for six liquid i

i~

effluent monitors and for eight gaseous. effluent monitors.

The monitors-

!.

were calibrated with NBS-traceable liquids and gases and cross-calibrated to solid scurces which will be utilized for. subsequent. calibrations.

The

liquid monitors were calibrated using sample chambers from Unit 2; each -

'

~

chamber was filled with water in which solutions of' known NBS-traceable

concentrations of Cd-109, Co-57, Cs-137, and-Co-60 were dissolved.

Ges monitor chambers were filled with known NBS traceable concentrations of j

Kr-85 -and Xe-133 for calibration and were cross-calibrated to solid Cl-36

)

and Sr-89/90 sources for future calibrations.

The inspector's review

included the high-range gaseous effluent monitors required under-i Item II.F.1, Attachment 1, of NUREG-0737.

I i

During the portion of. the inspection conducted February 2-3, 1987. the

!

inspector was informed by cognizant licensee. personnel that. the PERMSS, after approximately eight days of trouble-free operation, had experienced a

!

problem characterized by one or more liquid or gaseous effluent monitors

'

becoming inoperable and computer magnetic tape transport problems,. all apparently related to switching transients induced by power bus changeover.

,

!

This apparently occurred during switchovers-from' Essential; Bus."A" to "B,"

or vice-versa, to accommodate activities related to. work on systems which required Bus "A" or Bus "B" to be deactivated.. Such switchover is not

!

synchronous and involves voltage going to zero and then.being re-established from the other bus.

While the equipment is provided with power

,

conditioners, the conditioning equipment was designed to' eliminate noise

,

transients but not to accommodate a power drop to zero volts, no matter how

'

i short the outage interval.

The licensee is investigating corrective I

measures; however, it was also noted that-such switchovers are uncomon once

,

i the plant is in operation and would typically occur no more than once in an j

.18-month operating cycle.

i (Closed) 50-424/86-119-02:

Verify that ' damaged components of. the PERMSS -

'

computer have been replaced or repaired and that the PERMSS is operable.

Licensee representatives stated that. " head. crashes" had ' occurred on ' four

occasions during preliminary system testing and that the necessary repairs or replacement of components had been made. -It was-also stated that'a

,

!

" software" problem had been identified as a cause of the head crashes and

that this had been resolved by modifying the input program. Changes to the s

b f

_ _ _. _ _ _. _ _ _ _. _,. ~. _. _..., _ -. _... _.

,

, _ _. _

, _ _.,

-..... -,

,,~_-._..#_

.., _,..

., _ -.

.

.

- _

. _..

_

.

__

_..

_

.

.._

. _ _. _

_ _ _ _

,

.

b

-

.

,

.

program were made, documented, and tested and were determined.to resolve the difficulty.. The preoperational and functional ' tests tof the PERMSS were completed and the system was declared operational. - The inspector reviewed-

-

,

-

the completed PERMSS preoperational~proceduresLand determined that requisite tests and checks had apparently been completed.-.This item-.is considered

'

closed.

i (Closed)~50-424/86-137-02: Review incomplete preoperational~ test procedures i

remaining from Inspection 86-137 for PERMSS.

The inspector reviewed three

procedure subsections for the safety-related display console, identified as

,

" Digital Radiation Monitoring System," 1-3SD-01, and-17 procedure.

,

subsections of " Digital Radiation Monitoring l System," 1-3S0-02, all of which

,

had been previously noted as. incomplete.- All of the procedure subsections-

_

'

had been satisfactorily completed and Procedures 1-3SD-01 and 1-3SD-02

'

appeared to be 100% complete. This item is considered closed.

j (Closed) 50-424/86-119-03:

Review plant vent sampling design _ to verify that the number of sampling heads is consistent with ANSI N13.1-1969 (1974)

guidance.

ANSI N13.1-1969 states that a _ number of. sample heads _ (nozzles)

'

less than the number. specified in the.. standard, for a given size duct, is

acceptable if careful studies have been perfonned to show that uniformity of j:

composition exists throughout the cross-section of the duct. -The inspector reviewed. copies of design studies provided by the. licensee showing that turbulent flow would exist at the sampling heads and that mixing under such i

.

conditions would assure uniformity of composition.

This item is considered

.i

~

closed.

(Closed) 50-424/86-12-88:

Assure volume of vent' air sampled'- (1s)

i representative. of actual effluent activity; ;or that correction factors-

developed compensate for sample -scavenging mechanisms.

Design studies

,

[

provided -by the licensee's architect-engineering firm indicated the i

existence of highly turbulent airflow at : the sampling intake nozzle i

structure and also confirmed that -the principal. conditions of

,

i-ANSI N13.1-1974 have been met' relative to the. number of: nozzles per square

foot of duct cross section and -intake location. relative to transition or

'

flow changes.

Concerning " scavenging mechanisms," Inspector Followup-Item (IFI) 50-424/86-137-06, " Review applicant - (licensee) J evaluation - ~ of -

mechanisms of sample transport for iodine in'long sampling lines" was opened

in a previous inspection.

IFI 50-424/86-12-88 is considered closed.

(Closed) 50-424:

TMI Action Plant Items II.F.1-1, II.F.1.2. A and

-

4-II.F.1.2.B.

NURE6-0660, "NRC-Action Plan...," addresses requirements for:

equipment and procedures for the monitoring of noble gases and the sampling

,

and analysis of particulate.and iodine aerosols which could be= present in-gaseous effluents from nuclear power plants under accident. conditions. The

,

criteria are listed in Subsections II.F.1.1, II.F.1.2. A and II.F.1.2.B.

,

'~

Corresponding subsections in NUREG-0737 " Clarification of zTMI Action Plan.

'

.

Requirements" list additional information corresponding to the NUREG-0660

- criteria in Subsection II.F.1, Attachments 1 and 2.

In this inspection, and in previous. Inspection Reports86-100, 86-119,3and 86-137, the inspector

-

i-described evaluations and inspections of licensee's equipment and procedures

!

!

-.

'

,

.-

... _,

...-

.

.

_ _ _. _ _ _ _,.-

-. _. _ _.. _... ~ _... _.,..... _,

.

.

_

-

.

relating to the monitoring, sampling, and analysis of radioactive materials in plant gaseous effluent streams under normal and accident conditions.

Based on discussions presented in Section 5 of the Inspection 50-424/87-09, and in Inspections86-100, 86-119, and 86-137, the. licensee's installed instrumentation and sampling equipment is considered to meet the established criteria and is acceptable. This item is considered closed.

No violations or deviations were identified.

5.

Post-Accident Sampling System (PASS) (NUREG-0737 Item II.B.3; NUREG-0660 Items II.B.3.3 and II.B.3.4) (84523, 84524)

The Post-Accident Sampling System was previously reviewed.under Inspections86-119 and 86-137.

The only items of preoperational testing which remained to be reviewed were the completion of vendor. " hands-on" training (IFI 50-424/86-119-04) and resolution of sample return airflow into

)

!

containment (IFI 50-424/86-137-01).

In IFI 86-137-01, the inspector noted licensee difficulty in returning a

'

containment atmosphere sample gas volume back to containment.

The licensee

.

discovered that two' solenoid-actuated isolation valves on the gas return

!

line had a very small effective open area and were acting as flow.

restrictions.

The licensee replaced the two isolation valves, originally

designed for service in half-inch lines with two new valves which were designed to be used in one-inch lines.

- The modification worked

satisfactorily and the desired return flowrate was easily achieved with the existing air-moving device.

The IFI was closed on the basis of the installation of the larger valves and on the licensee's record of test results for this modification.

The inspector reviewed records and _ training material used in the vendor's training program, which was attended onsite by eight -licensee personnel.

All eight personnel successfully operated the PASS during the training period and all eight achieved passing scores on a written examination.

During the training program, the PASS was operated approximately-20 times without system malfunction.

Various aspects of the PASS were reviewed during Inspections86-119 and 86-137.

Based on the raaterial presented in the referenced inspections and on the above discussion, the inspector -concluded that the PASS was acceptable for full power operation.

However, the PASS will be further evaluated by RII at such time as the reactor has. accumulated at least 30 days of operation at full power.

At that time, the inspector will observe the collection, processing, and analysis of primary coolant samples using both the PASS and the normal process sampling facility.

(0pened) 50-424/87-09-01 (IFI) Evaluate PASS operation after plant has operated at least 30 days-- at full power and correlate analytical measurements against sample data obtained by normal operational sampling and analysis.

.

._-

-

.

- -

- - -.

.

.

.

_ _ _

__

,

.

-

.

(Closed) 50-424/86-12-83:

Completion of PASS training once the.- system becomes operational and updating tracking system to reflect this.

The inspector reviewed the vendor PASS training and applicable training records.

It was observed that the training tracking program had updated the appropriate training records and that the licensee's program appeared to be functioning properly. This item is considered closed.

(Closed) 50-424/86-12-86:

Completion of final PASS operational testing.

The inspector reviewed the licensee's operational testing program, determined that the preoperational, and hot functional testing had been completed.

Further, extensive use of the PASS during final vendor training provided additional verification of system operability.

This item is considered closed.

(Closed) 50-424/86-119-04: Review vendor hands-on (PASS) training scheduled for December 8-12, 1986.

The inspector reviewed training material and visuals used in the training program, reviewed examinations and scores, and reviewed licensee training records.

Based on the review, the inspector concluded that the training had been satisfactorily accomplished and this item is considered closed.

(Closed) 50-424/86-137-01:

Review corrective actions on return of post-accident sampling system (PASS) containment air sample flow back to containment. The licensee replaced two isolation valves with units having a larger effective internal diameter.

This action relieved excessive back-pressure which had interfered with return sample flow, permitting the system to return sampled air / gas back to containment.

This item is considered closed.

No violations or deviations were identified.

6.

Ventilation and Exhaust Gaseous Treatment Systems (84524)

The inspector reviewed the installation of a supplemental prefilter and tray-type II charcoal adsorber for the Technical Support Center (TSC). This was located in a heavily shielded space remote from the TSC personnel occupancy zones.

The filters and charcoal adsorbers in the heating and ventilation system of the TSC were also inspected.

These have been loaded with HEPA filters and the adsorber section filled with charcoal; however, D0P and freon leak testing of the system had not oeen accomplished as of the

'

end date of the inspection but is to be completed prior to Mode 2 operation.

(0pened) 50-424/87-09-02 (IFI).

Review results of DOP and freon leak tests of TSC HEPA filters and charcoal adsorbers.

As of the end date of the inspection, installation of HEPA' filters and bulk charcoal filling of the adsorber sections had been completed for the TSC, electrical penetration area, Control Room recirculation system, fuel handling building emergency exhaust system, and containment purge exhaust system. However, none of the D0P and freon leak tests had been performed as of the end date of the inspection.

,

..

..

-

. -

-.

-

--.

,

P

.

.

-

~

.

L

'

.

Systems which had not.been: loaded _with HEPA filters and charcoal includedi

'

laboratory hoods; steam jet air. ejector exhaust;--fuel handling building

normal ventilation, auxiliary building normal ventilation, and the ESF-

.

piping penetration packages.

On January 28-29,-1987, the inspector performed an in-office review of

.

.

Preoperational Test Procedures 1-3GK-02, "CB Safety Features Electrical

'

Equipment Rooms HVAC System;" 1-3GG-02,' '? Fuel Handling Building Post i

Accident HVAC System;" and 1-3GK-02, " Control Room HVAC System."

These

items had been requested by the inspector during the course of the inspection but had not been available for review during the inspector's site

visit of January 12-13, 1987,- and were subsequently mailed to the inspector and were received January 26, 1987, and January 28, 1987.

,

Each of the three preoperational test procedures appeared to.have been >100% -

,

completed.- A spot-check of test logs, change requests, and review comment ~

sheets against procedure entries showed good correlation, and all necessary

.

sign-offs and approvals appeared to have been made. The reviewed procedures

,

did not include the leak tests required under ANSI N510-1980 and these remained to be performed.

'

The inspector also reviewed laboratory tests which had been performed ~ on carbon (charcoal) loaded into ESF air treatment systems in accordance with Technical Specifications.

All tests had been performed by ~ a qualified

,

analytical contractor and all tests indicated methyl iodide retention of

'

99.98% or better when tested against a methyl iodide challenge aerosol at

,

30 C and 70% relative humidity using the test procedures specified in ASTM D.3803.

No violations or deviations were identified.

!

7.

Liquid Radwaste Processing (84523)

The inspector reviewed progress toward inst!allation of contractor _. liquid

'

radwaste processing equipment in the Interim Radwaste Building.

The contractor has installed eight demineralizer vessels and one filtration

vessel. Additional equipment has been supplied for the transfer, dewatering and storage of spent resins.

Licensee and contractor personnel were

conducting hydrostatic pressure testing of the vessels and connecting hoses.

at the time of the inspection.

It was also noted that a solid waste compactor had been moved into the building.

[

The inspector also reviewed the contractor's manual for system operation.

!

It was also noted that the ~ contractor topical report on the waste processing system had been submitted to NRR for review and had been accepted.

Acceptance was documented in a letter, dated September 6,1985, from

.

C. O. Thomas, Chief Standardization and Special Projects Branch, Division

'.

of Licensing, to R. T. Haelsig, Nuclear Packaging, Incorporated, Federal Way, Washington 98003.

i No violations or deviations were identified.

l l

I

. _,

_,,... - _,,..,

,m.

- - _ _ -,. - -

,

- n..

.-..,,u.,_.-

,..-_a

.. _ - - - -. - -.

.

.

. _

_

_ _. _

_.

.__

__.

j

<

..

8.

Licensee Action on Previously Identified : Inspector Followup Items (84523, 84524)

E (Closed) 50-424/86-12-23:

Completion of the installation and testing of TSC

,-

ventilation system and qualification of cognizant personnel. The inspector l-verified that the TSC : ventilation system had been installed and that tests, with the exception.of leak. testing of. HEPA filters and charcoal adsorbers, n

had been completed and that maintenance procedures had been established. A new.IFI has been established.for leak testing of the TSC'HEPA filters and charcoal adsorbers. This-item is considered closed..

,

>

(Closed) 50-424/86-12-32:

Complete. equipment installation ' and-. ensure -

operational and procedural adequacy for. post accident. gas and particulate effluent sampling.

All preoperational inspections,were completed during this inspection and the post accident gas and - particulate eff_luent -

monitoring and sampling systems were found to be adequately installed and tested and met all applicable criteria.

l A concern had been previously raised about ALARA aspects of. obtaining the plant vent samples as a result of the proximity of HEPA'and charcoal ventilation treatment systems near a-point which could. be occupied by i

persons detailed to. collect samples.

The licensee prepared an ALARA

evaluation, dated February _2,1986, which concluded that 'the HEPA and.

charcoal system of principal concern was the post LOCA purge system.

The

'

licensee determined that this system was a backup to another system and was l

not.likely to be used.in a design basis. accident and that.such operation

!

need not be assumed when performing the time-motion study for post-accident j

sampling of the plant vent required in IIF.1, Attachment 2.of NUREG-0737.

i The inspector concurred in the licensee's evaluation.. On the basis of the i

licensee's analysis and on the discussion above, 'this item is-considered closed.

'

l (0 pen) 50-424/86-119-05:

Review the gamma spectroscopy system calibrations

-

for various geometries at different shelf heights, coincidence summing j

j effects for gas geometries and gas efficiency determinations;for energies D

i greater than 500 kev. This item was not addressed during the inspection and remains open.

(0 pen)50-424/86-119-06:

Review results of applicant (licensee) analyses of spiked, simulated liquid waste sample containing Fe-55,- Sr-89, Sr-90, and

,

!

H-3.

This item was not addressed during the inspection and remains open.-

.

lj (0 pen) 50-424/86-137-03:

Review preoperational. procedures for the boron recycle system and waste evaporator.

This subject was not addressed during the inspection. This item remains open.

.

I (0 pen) 50-424/86-137-04:

Review preoperational tests of the. waste gas system which were to be completed by December 15, 1986.

This subject _was not addressed during the inspection. This item remains open.

.

i

-.

-

.

-. -

--

..

. -. - --

-

-

-

.

(0 pen) 50-424/86-137-06:

Review applicant (licensee) evaluation of mechanisms of sample transport for_ iodine in long sampling lines. Licensee-evaluation of this question had not been completed at the time of the-inspection. This item remains open.

(0 pen) 50-424/86-119-01:

Review laboratory procedures for air cartridge placement, gamma system efficiency checks and performance charts, audit frequency, and sample preservation.

This item was not reviewed in this inspection an remains open.

(0 pen) 50-424/86-119-07:

' Modify 90 bend on the intake line of the environmental air samplers.

This item was not addressed during the inspection and remains open.

.

..

_

_

--...