ML18052B417

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Insp Rept 50-255/87-28 on 871116-25.No Violations or Deviations Noted.Major Areas Inspected:Implementation of Generic Ltr 83-28,including Equipment Classification,Vendor interface,post-maint Testing & Reactor Trip Sys Reliability
ML18052B417
Person / Time
Site: Palisades Entergy icon.png
Issue date: 12/16/1987
From: Gardner R, Neisler J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML18052B416 List:
References
50-255-87-31, GL-83-28, NUDOCS 8712210272
Download: ML18052B417 (5)


See also: IR 05000255/1987028

Text

U.S. NUCLEAR REGULATORY COMMISSION

REGION III

Report No. 50-255/87031(DRS)

Docket No. 50-255

License No. DPR-20

Licensee:

Consumers Power Company

212 West Michigan Avenue

Jackson, MI

49201

Facility Name:

Palisades Nuclear Generating Plant

Inspection At:

Covert, Michigan

Inspection Conducted:

November 16-25, 1987

Inspector: R .t\\. ~-~.JW,v ~

J. H. Neisler

R.t\\-~V\\1---

Approved By:

R. Gardner, Chief

Plant Systems Section

Inspection Summary

Inspection on November 16-25, 1987 (Report No. 50-255/8703l(DRS))

12-/t~/~7

Date

Areas Inspected:

Routine announced inspection of the licensee

1 s implementation

of Generic Letter 83-28 in the areas of equipment classification, vendor

interface, post maintenance testing and reactor trip system reliability.

Closed TI 2515/64RI and TI 2515/91.

Results:

No violations or deviations were identified .

8712210272 871216

~DR ADOCK 05000255

PDR

DETAILS

1.

Persons Contacted

Principle Licensee Employees

  • D. P. Hoffman, Plant Manager
  • R. E. McCaleb, Quality Assurance Director
  • C. S. Kozup, Technical Engineer
  • J. G. Lewis, Technical Director
  • R. D. Oroz, Engineering and Maintenance Manager

H. C. Tawney, Mechanical Maintenance Supervisor

T. C. Saarela, System Engineer, Mechanical

C. R. Ritt, Administration Supervisor

R. B.

K~sper, *Electrical Mainteriance Supervisor

R. S. Westerhof, System Engineer, I&C

P. A. Gist, Document Control Clerk

W. L. Roberts, Project Engineering

  • Denotes those persons attending the exit interview.

2.

TI 2515/64Rl (Closed) TI 2515/91 (Closed)

a.

Equipment Classification

The inspector selected five components in the reactor protection

system (RPS) and ten components in the containment spray system for

examination during this inspection.

The components selected were:

RPS

Trip contactors

Manual trip breaker

Rod drive clutch power supply

Rod drive motor

Rod drive clutch

Containment Spray System

Containment spray pump P~54A

Containment spray pump motor

2400 volt circuit breaker 152-210

Fl ow transmitter FT-0301

Valve CK-3181

Valve CV-3001

Level transmitter LT 0437A

Valve CV-3029

Valve CV-3031

Valve CK-3239

(1) The inspector reviewed the licensee's equipment classification

(Q-List) procedure and the Palisades Q-List.

The licensee ha~

established a comprehensive classification system that

encompasses all plant structures, systems, components, and

activities. The inspector selected components and activities

for comparison with the Q-List to verify whether these

components and activities were being correctly classified as

safety related.

Each of the items selected was correctly

classified on the Q-List.

2

(2)

To determine the level of plant management oversight, the

inspector reviewed plant procedures controlling maintenance,

modifications, procurement, inspection, and testing of

safety-related components.

For activities impacting

safety-related structures, systems, and components, the

inspector reviewed quality assurance procedures, audits,

surveillance activities, and corporate level procedures~

(3)

Equipment classification is controlled_by Administrative

Procedure 9.30,

11Q-List.

11

The procedure establishes

responsibilities and method's for -assuring the proper

classification of plant structures, systems, components, and

activities.

The addition or deletion of items on the Q-List

is reviewed and approved by the quality assurance organization

prior to the initiation of any action that affects the item's

classification.

(4)

The inspector reviewed approved procedures issued by corporate

and plant management for procurement, maintenance, modifications,

inspection, testing, and surveillance activities affecting

safety-related structures, systems, and components.

(5)

The inspector reviewed procedures established to control the

training and indoctrination of personnel performing activities

affecting safety-related structures, systems, and components.

Included in the review were procedures for training maintenance

and I&C personnel, staff and management personnel and quality

assurance personnel.

The inspector reviewed personnel

training and indoctrination records to verify that the required

training was being accomplished.

In addition to the usual

practice of training personnel for activities affecting

safety-related components, Palisades has included the requirement,

as a first step on their work orders, that the supervisor/foreman

verify the qualifications of the personnel assigned to

perform the activity.

Each maintenance supervisor is provided

a matrix showing the training and qualifications of each

individual assigned to his section.

(6)

The inspector reviewed five audit reports of safety-related

activities that had been performed by the off-site corporate

quality assurance organization and twenty surveillance reports

of safety-related activities that had been performed by the

on-site quality assurance department.

Both quality assurance

groups maintain schedules of planned audits and surveillances

for safety-related activities at the facility.

(7) The corrective action program for safety related activities

is controlled by Administrative Procedure 3.03, "Corrective

Action,

11 and other quality assurance, engineering, and corporate

procedures.

The inspector's review of corrective action for

audit and surveillance findings revealed that the corrective

actions for those findings were adequate, timely, and complete.

3

(8) Review and evaluation of information concerning malfunctioning

equipment is controlled by the licensee's corrective action and

deviation procedures.

The Corrective Action Review Board (CARB)

and the Plant Review Committee (PRC) review malfunctioning or

nonconforming equipment to determine whether an identical

replacement could be expected to perform reliably.

(9) The inspector reviewed the licensee's modification control

program and selected modifications to -safety related systems.

The modification documentation including drawings, work

orders, and inspection documentation were clearly identified

as safety-related.

No violations or deviation were identified.

b.

Vendor Interface

The inspector reviewed the licensee's Administrative Procedure 10.45,

"Vendor Manual Control." This procedure establishes responsibilities

and methods to assure that vendor technical information is reviewed

and evaluated, controlled, and maintained current by the document

control section.

Vendor information for five RPS components and

ten core spray components were reviewed for completeness and to

determine whether the information on file accurately reflected the

installed equipment.

Guidance provided in the vendor manuals has

been included in the maintenance, test, and inspection procedures

used in the facility.

No components were identified as being

manufactured by vendors who have since gone out of business.

The licensee's procedures controlling maintenance anJ modifications

  • and administrative procedures pertaining to vendor technical

information were reviewed.

The procedures were determined to be

adequate to control replacement of equipment in situations where a

vendor goes out of business or will not supply adequate information

to the plant.

The licensee is participating in the Nuclear Utility Task Action

Committee (NUTAC) and the Nuclear Plant Reliability Data System

(NPRDS).

The inspector determined that procedures were in place to

require periodic surveillances of vendors of safety-related

components and services.

Procedures have been established for the

reporting and evaluation of NPRDS and SEE-IN information.

No violations or deviations were identified.

c.

Post Maintenance Testing

The inspector selected a containment spray pump, three motor-operated

valves, one 2400 volt circuit breaker, and a spray pump motor.

For the selected components, the inspector determined the following:

4

(1)

Post maintenance testing and surveillances are controlled by

written procedures.

Th~ inspector reviewed completed work

orders involving both preventive and corrective maintenance.

Each work order indicated that the required post maintenance

testing had been performed.

(2) Criteria and responsibilities for maintenance and for designating

maintenance activities as safety-related and non-safety-related

have been established in the work request/work order initiation

procedures.

Inspection of post maintenance tests is controlled

by the quality assurance/quality control inspection program.

(3) Methods for performing functional testing following maintenance

of safety-related components have been developed and are

delineated in published plant procedures, operator surveillance

procedures, and in maintenance and I&C procedures.

(4) *The inspector reviewed completed work orders and supporting

documentation retrieved from document control records storage.

The documentation contained approvals of work requests/work

orders, the identity of persons who performed the activity, and

the individuals who performed post maintenance reviews and tests.

c.

Reactor Trip System Reliability

The Palisades design does not include reactor trip breakers. The

licensee has established a maintenance and surveillance program for.

the control rod drive contactors, the control rod drive clutches,

and the manual trip breaker.

The inspector verified that maintenance

and inspection of these items is beirig performed according to their

manufacturer 1 s instruction.

The inspector verified that monthly on-line functional testing is

being performed on the bistable/auxiliary trip units, the 2-out~of-4

matrix logic, and clutch power trip circuits.

The manual trip

breaker 1 s preventive maintenance and functional testing is performed

  • at each refueling outage.

No violations or deviations were identified.

3.

Exit Interview

The inspector met with licensee representatives (denoted under Paragraph 1)

at the conclusion of the inspection and summarized the scope and findings

of the inspection.

The licensee acknowledged the inspector 1 s comments.

The inspector also discussed the likely informational content of the

inspection report with regard to documents or processes reviewed by the

inspector during the inspection.

The licensee did not identify any such

documents or processes as proprietary.

5