ML18044A405

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IE Insp Rept 50-255/79-17 on 791001-05,09-12,15-19,25-26 & 29-31.Noncompliance Noted:Failure to Take Required Chemistry Sampling & Violation of Procedural Limit on Refueling Water Level
ML18044A405
Person / Time
Site: Palisades 
Issue date: 11/21/1979
From: Boyd D, Jorgensen B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML18044A403 List:
References
50-255-79-17, NUDOCS 8001100325
Download: ML18044A405 (6)


See also: IR 05000255/1979017

Text

U. S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-255/79-17

Docket No. 50-255

Licensee:

Consumers Power Company

212 West Michigan Avenue

Jackson, MI

49201

Facility Name:

Palisades Nuclear Generating Plant

Inspection At:

Palisades Site, Covert, MI

License No. DPR-20

Inspection Conducted:

October 1-5, 9-12, 15-19, 25, 26, and 29-31, 1979

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Inspector:AB. L . .forge'Jt.en

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Approved BylfttD. c.Jrdyd,~Chief

Reactor Projects Section 3

Inspection Summary

Inspection during October, 1979 (Report No. 50-255/79-17)

Areas Inspected:

Routine resident inspection program for October, 1979,

including records; review and audit; maintenance; and refueling prepara-

tions and activities.

The inspection involved 90 onsite inspection

hours.

Results:

Of the four areas examined, no items of noncompliance or devia-

tions were identified in three areas.

Two items of noncompliance

(Infraction-missed required chemistry sampling; and, Deficiency-violated

procedural limit on refueling water level) were identified in the remaining

area.

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1.

DETAILS

Persons Contacted

  • J. G. Lewis, General Manager - Palisades
  • H. W. Keiser, Plant Superintendent
  • H. J. Palmer, Technical Superintendent
  • R. E. McCaleb, Quality Assurance Superintendent
  • B. L. Schaner, Operations Supervisor
  • G. H. R. Petitjean, Technical Engineer

C. Thomas, Mechanical Maintenance Supervisor

J. A. Meineke, Reactor Engineer

D. L. Beach, Electrical Maintenance Supervisor

R. E. Mieras, Shift Supervisor

K. Ridley, PRC Secretary

  • Denotes those present at exit interview on November 2, 1979.

The inspector also had discussions with various members of the

operations, maintenance, technical and administrative staffs.

2.

Plant Records

This inspection included an examination of the licensee's system for

development, review and retention of important facility records.

The overall program is defined by and administered in accordance

with Administrative Procedures Sections 10, "Plant Documents" and

11, "Plant Records".

Responsibilities are assigned for compiling,

transmitting and storing records and a matrix has been developed to

control record retention in compliance to various requirements.

Technical Specification 6.10 directly addresses numerous types of

records which must be retained, and provides required retention

times.

For this inspection, the inspector verified the licensee's control

matrix to be consistent to the technical specifications.

The onsite

document storage facility was examined and selected records identi-

fied in the technical specifications were verified present and

proper, as follows:

a.

facility operation records and logs

b.

safety-related maintenance records

c.

reportable occurrence records

d.

records of reactor tests and experiments

e.

records of changes to operating procedures

f.

chlorine treatment records

g.

limited cycle log

h.

Plant Review Committee minutes

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Micro-reproduction and duplicate offsite storage practices were

discussed with document control personnel.

The inspector noted the "Limited Cycle Logbook" has apparently not

been updated since 1977.

Discussions with the licensee indicate the

information centralized in this log remains retrievable from other

protected records, and the licensee agreed to assign an engineer to

update this document on a regular basis.

No items of noncompliance or deviations were identified.

3.

Review and Audit

The activities of the licensee's Plant Review Committee (PRC) during

1979, as documented in routine and special PRC Meeting Minutes, were

reviewed during this inspection.

The controlling primary documents

used in this review were Technical Specification 6.5.1 and Adminis-

trative Procedure Section 3. Compliance to the following items was

specifically examined:

a.

meeting frequency

b.

membership and quorum

c.

items reviewed

(1) potential unreviewed safety questions per 10 CFR 50.59

(2)

technical specification noncompliances

(3)

technical specification proposed changes

(4)

selected procedure changes

(5)

safety-related plant modifications

(6)

reportable events

(7)

selected tests and experiments

No items of noncompliance or deviations were identified.

4.

Maintenance

Selected maintenance activities were reviewed to ascertain they were

conducted in accordance with requirements.

The following specific

activities were examined:

a.

overhaul of boric acid pump, P-56A

b.

vessel head reset

c.

control rod guide rack run-in and hook-up

The examination included direct observation at the jobsite for each

item.

The inspector verified compliance to limiting conditions

for operations with an out-of-service component; obtaining of prior

approval; availability and utilization of procedural controls;

use

of qualified personnel and independent verification when appropri-

ate; and proper development of records on the activity.

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No items of noncompliance or deviations were identified.

5.

Refueling

This inspection included an examination of licensee activities,

procedures and records relating to the reactor refueling performed

during the unit outage which commenced September 8, 1979.

New fuel

receipt, inspection, and storage preparatory to the refy7ling was

examined and documented in previous inspection reports,-

including

review of pertinent procedures.

Licensee examination of recycle and

spent fuel elements for this refueling was minimal, did not include

fuel sipping, and was not specifically examined by the inspector.

a.

Procedures

The following procedures and checklists were reviewed for

content, functional and administrative controls, and proper

implementation:

(1)

CRD0-1 "Disconnecting Control Rods from CRDM' s"

(2)

CRD0-4 "Uncoupling Control Rod from its CRDM When Standard

Procedure CRD0-1 is Not Able to be Used"

(3)

FHS0-1 "Spent Fuel Pool Elevator Periodic Testing"

(4)

FHS0-2 "Refueling Procedure"

(5)

CL AS.14-1 "Refueling Operations Prerequisite Master Check

Sheet"

(6)

CL A5.14-2 "Refueling Operations Shift Check Sheet"

(7)

CL 3.3 "Containment Integrity"

(8)

CL 35 "Neutron Monitors System Check List"

(9)

CL 28-1 "Refueling Communication Check List"

(10) CL 28-2 "Fuel Elevator Check Sheet"

(11) CL 28-3 "Fuel Pool Refueling Machine Check Sheet"

(12) CL 28-4 "Refueling Machine Checklist"

(13) CL 28.5 "Tilt Machine Check Sheet"

(14) CL 28-6 "Refueling Ventilation CP,eck Sheet"

l/

IE Inspection Reports No. 050-255/79-11; No. 050-255/79-13

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(15) Special Test Procedure T-94, "Core Verification"

The procedures were determined to be inclusive of and consistent

with the technical specifications' limiting conditions.

b.

Activities

A number of requirements are in effect only when fuel handling

is in progress.

These items were checked with reference to the

Fuel Handling Log, which documents all the fuel movements.

Two

problems were identified. First, the licensee is required by

Technical Specification 3.8.1.g to check the primary coolant

system boron concentration on each shift when refueling activi-

ties are being carried out in the reactor.

This is to assure

the required shutdown boron concentration is continuously

maintained.

The Fuel Handling Log documents that refueling

activities (fuel handling) were conducted on the "A" shift on

October 2, 1979.

No boron sample results for this shift were

documented on CL AS.14-2, however, and discussions with plant

chemistry personnel established a boron sampel had not been

collected and analysed for that shift. Failure to perform the

required sampling and analysis is an item of noncompliance with

the referenced Technical Specification and is an Infraction.

The second problem relates to procedural controls stated in

CLA5.14-2, which is part of FHS0-2, "Refueling Procedure." The

check list states the minimum reactor cavity and spent fuel

pool water level for fuel handling to be one foot below the

surface skimmers.

The Fuel Handling Log documents fuel handling

on the "A" shifts of October 11 and 12, 1979, while the checklist

shows water level to have been 1.5 and 2 feet, respectively,

below the surface skimmers during those shifts.

In that implemen-

tation of procedures governing refueling operations is a require-

ment of Technical Specification 6.8.1.b, handling fuel with the

water level lower than permitted by procedures is an item of

noncompliance.

This item is a deficiency.

c.

Direct Inspection

The inspector directly observed fuel handling activities in the

reactor cavity and in the spent fuel pool on October 4 and 10,

1979. The following items were checked:

(1)

refueling machine operation and indexing

(2)

refueling area ventilation

(3)

radiation and criticality monitoring

(4)

communications

(5)

fuel accountability

(6)

housekeeping

(7)

cavity and pool water level

(8)

presence and utilization of procedures

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l

Control room activities were also witnessed on several shifts,

the inspector verifying compliance with staffing requirements

for the refueling shutdown condition.

No other items of noncompliance or deviations were identified.

6.

Management Interview

A management interview, attended as indicated in Paragraph 1, was

conducted on November 2, 1979.

The inspector summarized the scope

and findings of the inspection, specifically stating the two identi-

fied items of noncompliance.

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