ML19350C992

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IE Insp Repts 50-282/81-01 & 50-306/81-01 on 810105-08. Noncompliance Noted:Failure to Comply W/Audit,Record Storage, & Receipt,Storage & Handling Requirements
ML19350C992
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/09/1981
From: Baker K, Grobe J, Jackiw I, Schulz R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19350C984 List:
References
50-282-81-01, 50-282-81-1, NUDOCS 8104130038
Download: ML19350C992 (24)


See also: IR 05000282/1981001

Text

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U.S. NUCLEAR REGULATORY COMMISSION

OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Reports No. 50-282/81-01; 50-306/81-01

Docket Nos. 50-282; 50-306

Licenses No. DPR-42; DPR-60

Licensee: Northern States Power Company

414 Nicollet Hall

Minneapolis, MN 55401

Facility Name:

Prairie Island Nuclear Generating Plant, Units 1 and 2

Inspection At: Red Wing, MN

Inspection Conducted: January 5-8, 1981

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Inspectors:

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  1. . A. Grobe

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Approved By:

K. 7Idker, Chief

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Nuclear Support Section 2

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Inspection Summary

Inspection on January 5-8, 1931 (Reports No. 50-282/81-01; No. 50-306/81-01)

Areas Insjected: Announced inspection in the following areas:

audit

program- receipt, storage and handling of equipment; records; document

contro'.; design changes; housekeeping and cleanliness; procurement; test

and reasurement equipment; and fire prevention and protection programs.

The inspection involved a total of 96 inspector-hours onsite by three NRC

inspectors including 0 inspector-hours onsite during off-shifts.

Results: Of the nine areas inspected, no apparent items of noncompliance

or deviations were identified in five areas, four items of noncompliance

were identified in four areas (failure to comply with audit requirements -

paragraph 6; failure to meet record storage requirements - paragraph 5;

failure to meet receipt, storage and handling requirements

paragraph 4;

failure to follow design change control procedures

paragraph 8).

8104130 0 3 8

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DETAILS

1.

Persons Contacted

  • F.

P. Tierney, Plant Manager

  • K.

J. Albrecht, Superintendent, Quality Assurancs

  • D. J. Silvers, Quality Assurance Engineer
  • W.

Gauger, I & C Supervisor

  • T.

Reding, Document Control Coordinator

  • R. Warren, Office Manager
  • R. Hansen, Quality Assurance Engineer
  • L. Brunner, Warehouse Supervisor
  • J. Nelson, Superintendent of Maintenance
  • E.

C. Liebeg, Administrative Aid

~*W.

R. Waldron, Training Supervisor

  • D.

D. Althaus, Plant Services Supervisor

  • J..B. Brokaw, Superintendent - Operations and Maintenance
  • D. R. Brown, Production Engineer
  • D. J. Mendele, Superintendent - Operations Engineering
  • A. C. Johnson, Radiation and Chemistry Coordinator
  • C. H. Harmsen, Production Engineer
  • D. A. Schenlke, Superintendent Radiation Protection

NRC Region III

  • I.

N. Jackiw, Reactor Inspector

  • R.

D. Schulz, Reactor Inspector

  • J. A. Grobe, Reactor Inspector
  • C. D. Feierabend, Reactor Inspector
  • B. L. Burgess, Reactor Inspector
  • W.

S. Little, Chief, Project Section 2

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  • Denotes those present at the exit interview.

2.

Licensee Action on Previous Inspection Findings

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(Closed) Unresolved Item (50-282/79-21; 50-306/79-18):

The periodic

audits which had not been conducted, were conducted in 1980. These

audits were:

3 ACD 2.2, 5 ACD 2.2, 5 ACD 2.3, 5 ACD 2.5, 5 ACD 7.1,

and 5 ACD 8.4 However, the licensee was in noncompliance with their

Operational Quality Assurance Plan in that an audit of 3 ACD 9.1,

Surveillance Program, had not been done since the directives inception

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in March of 1979.

(See paragraph 6.)

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18): The require-

ment for administrative controls to conduct periodic inspections of

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the storage areas as per ANSI N45.2.2 - 1972, paragraph 6.4.1 and the

actual conducting of such inspections was not implemented or performed.

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The requirement for administrative controls for handling of safety-

related material and for hoisting equipment used in the handling of

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safety-related equipment as per ANSI N45.2.2 - 1972, paragraph 7

were still not implemented or performed.

The above two items resulted in an item on noncompliance.

(See

paragraph 4.)

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18): The require-

ment for administrative controls for maintenance and care of items

in storage, including shelf life, as per ANSI N45.2.2 - 1972, para-

graph 6.4.2 was not implemented or performed. This resulted in an

item of noncompliance.

(See paragraph 4.)

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18):

Levels of

storage have been established in 5 ACD 8.2, Inventory Control.

Warehouses have been designated for "B" Levels of Storage and the

licensee has recognized the need for certain items to be stored

indoors, but care of items, including shelf life, to prevent damage,

deterioration, or contamination need to be firmly established. This

area will_be reviewed during subsequent inspections.

(Open) Unresolved Item (50-282/79-21; 50-306/79-18):

I&C Section

Work Instruction, SP-1 Revision 2, Inventory Control, does not have

a provision for QA inspection of QA-1 items returned to storage.

The I&C Supervisor, will propose a change to this procedure and it

will be reviewed during is subsequent inspection.

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18): A record

index has been established that lists retention times.

The licensee

is in the process of building a record vault, scheduled for completion

in 1981. Ilowever, access control has not been established and records

are located in many places, some not in fireproof cabinets. This has

resulted in a violation which is stated in Appendix A (See paragraph 5.)

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18): The authorized

users of the controlled drawing files in the I&C work area, electrical

work area, and electrical engineer work area were designated and the

responsible person for the files was aware of access control require-

ments.

Procedure, 5 ACD 4.4 was revised October 4, 1980 and addressed

the steps to be taken when a controlled drawing file was cancelled.

(Open) Unresolved Item (50-282/79-21; 50-306/79-18): Discrepancies

noted in the licensee's procedure regarding the plant training

program. During a recent plant reorganization, the plant training

department has been assigned to report to the corporate office who

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now has responsibility for plant training and is ir. the process of

rewritting current training ACD's.

These procedures will be reviewed

during a followup inspection.

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18): The inspector

found that 5 ACD 2.1, Quality Assurance Program Boundry, has been

totally rewritten.

It now includes the Q-list and the Q-list extension.

The Q-list extension has been reviewed and approved for use.

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The inspector also noted that, in the new plant organization, the

Superintendent-Quality Assurance reports directly to the Plant

Manager.

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18):

Responsi-

bilities for review and incorporation of requirements into station

level ACD's. The inspector verified that the Operational Quality

Assurance Plan and station ACD's assign responsibility for review of

General Office ACD's to the station Quality Assurance Section. The

QA section is responsible for incorporating new General Office

requirements in station administrative control directives.

(Closed) Deviation (50-282/79-21; 50-306/79-18):

Commitment to

complete the requirements of IEB 78-05 was not met.

The inspector

verified that a method for tracking commitments has been implemented.

The licensee also stated that plana are underway to computerize the

commitment tracking system.

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18:

Duty Engineer

to act as Chairman /Vice Chairman of OC in their absence. The inspector

notes that it is acceptable for the Plant Manager to appoint the Duty

Engineer as Vice Chairman provided the Duty Engineer is a member of the

OC.

(Closed) Unresolved Item (50-282/79-21; 50-306/79-18):

Independent

verification of electrical jumpers and lifted leads. The inspector

verified that plant requirements regarding independent verification

had been upgraded. Plant 5 ACD 3.9, issued on August 29, 1980,

includes requirements for independent verification of bypass instal-

lation and removal. The verification is done by an individual

independent of the work activity and excludes the first line super-

visor responsible for the work activity.

(Closed) Noncompliance (50-282/79-21; 50-306/79-18):

Failure to

follow procedure concerning design change control. The inspector

verified that all corrective actions regarding this item of non-

compliance had been completed as stated in the licennee's response

dated October 31, 1979.

3.

Procurement Program

The procurement program was reviewed to ascertain its conformance

with regulatory requirements and commitments in the Operational

Quality Assurance Plan. Procurement documents were checked for

technical requirements, QA plan requirements, 10 CFR 21 provisions,

specific identification of items, and statements concerning access

to the supplier's plant or records for purposes of audit. Procedures

were reviewed to determine if responsibilities were assigned in

writing for:

(a) initiation of procurement documents, (b) review

and approval of procurement documents, (c) making changes to procure-

ment documents and (d) basis for classification of procurement

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items. An approved vendors list was reviewed, along with the basis

for classification.

Procurement documents for various systems were

checked, along with the supplied materials documentation, including

traceability to the item.

a.

Documentation Reviewed

OQAP 6.0, Procurement Document Control

5 ACD_7.0, Uniform Nuclear Plant Procurement Process

3 ACD 6.1, Uniform Nuclear Plant Procurement Process

b.

Findings

No items of noncompliance or deviations were identified.

4.

Receipt, Storage and Handling of Equipment and Materials Program

Receipt, storage and handling of equipment and materials was reviewed

to ascertain whether the licensee is implementing a QA program that

is in conformance with regulatory requirements and commitments in

the Operational Quality Assurance Plan and implementing procedures

The inspector verified that responsibilities were assigned for receipt,

acceptance, release, storage, and handling of items. Nonconforming

items were reviewed for identification, segregation, control, and

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release. Procedures were reviewed for levels of storage and appropriate

environmental conditions, including shelf life,

a.

Documentation Reviewed

3 ACD 6.1, Uniform Nuclear Plant Procurement Process

5 ACD 8.1, Receiving Process

5 ACD 8.2, Inventory Control

5 ACD 8.3, Weld Material Control

5 ACD 8.4, Control of Nonconforming Items

SWl-I&C-SP-1, Spare Parts Inventory Control

OQAP 15.0, Handling, Storage and Shipping

OQAP 10.0, Identification and Control of Materials, Parts and

Components

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OQAP 11.0, Inspection

OQAP 9.0, Control of Purchased Material, Equipment and Service

OQAP 17.0, Nonconforming Materials, Parts or Components

b.

Findings

Noncompliance (50-282; 306/81-01-01)

10 CFR 50, Appendix B, Criteria XIII states in part, " Measures

shall be established to control the handling, storage, shipping,

cleaning, and preservation of material and equipment in accordance

with work and inspection instructions to prevent damage or

deterioration."

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Prairie Island's OQAP commits to complying with ANSI N45.2.2 - 1972

and ANSI N18.7 - 1976 to fulfill the requirements of 10 CFR 50,

Appendix B, Criteria XIII.

Contrary to the ANSI requirements, Operational Quality Assurance

Plan, and implementing procedures, the following examples of non-

compliance were noted:

ANSI N45.2.2 states in paragraph 6.2 that periodic inspections

shall be preformed to assure that storage areas are being main-

tained in accordance with these requirements.

ANSI N45.2.2

states in paragraph 6.4.1 that inspections and examinations

shall be performed and documented on a periodic basis to assure

that the integrity of the item and its container is being main-

tained. ANSI N45.2.2 states in paragraph 8 that inspection and

examination records shall be prepared as required by this

standard. Periodic inspections are not being done on the

storage areas or on items to assure their integrity or mainte-

nance, to prevent degradation, deterioration, physical change,

and loss of identification and traceability.

ANSI N45.2.2 states in paragraph 7.4 that an inspection program

shall be established for equipment and rigging. An inspection

program has not been established for equipment and rigging.

ANSI N45.2.2 paragraph 6.2.1 states in part, " Access to storage

areas for Level A, B and C items shall be controlled and limited

only to personnel designated by the responsible organization."

Prairic Island's Inventory Control Procedure 5 ACD 8.2, establishes

this requirement in paragraph 6.1.3.

An access list of personnel,

authorized access to the Receiving Inspection, Hold, and Storage

Areas had not been generated.

In addition, the rear doors to

Warehouse A and B, Level B storage areas were not locked permit-

ting uncontrolled access.

Prairie Island's OQAP states in paragraph 15.2 that storage

facilities shall be arranged to facilitate control of the

safety-related items. ANSI N45.2.2 states in paragraph 6.3.1,

"All items shall be stored in such a manner as to permit ready

access for inspection or maintenance without excessive handling

to minimize risk of da7 age.

Storage of items in Warehouse A

and B indicate a storage system based on space availability and

convenience, rather than the categories of safety-related and

non-safety-related.

Numerous items, bath safety-related and

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non-safety-rclated, are stored in the same areas due to a short-

age of space.

Items are not arranged to permit ready access for

inspection or maintenance without excessive handling, to minimize

risk of damage, as isles are blocked with materials and items are

stacked high on racks or cribbing.

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The OQAP commits to ANSI N18.7, which requires in paragraph S.2.13

that procedures shall be established and implemented to ensure

that purchased materials and components associated with safety-

related structures or systems are properly documented to show

compliance with applicable specifications, identified and

stored to protect against damage, deterioration or misuse.

Flanges, fittings, nuts and bolts which had been turned over

from construction had not been inspected and documented for

damage, corrosion, or heat traceability. Documentation did not

indicate a review had been done of the original purchase order

and test report to assure compliance with applicable, safety-

related specifications, codes and standards. A three inch,

standard tee, was incorrectly identified as being a three inch,

X-Strong tee, with heat traceability number 680A. The heat

traceability number, 680A, was for the X-Strong tee, representing

its chemical and physical properties. These identification and

control measures do not protect against damage, improper substi-

tution, or misuse.

ANSI N45.2.2 paragraph 6.3.3 states, " Hazardous chemicals,

paints, solvents, and other materials of a like nature shall be

stored in well-ventilated areas which are not in close proximity

to important nuclear plant items." Materials marked " Flammable

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liquid" were in close proximity to important nuclear plant

items. A primer, designated Phenoline, and DOT were located

next to safety-related welding rod and a electric motor for a

containment fan coil unit.

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ANSI N45.2.2 paragraph 6.4.2 states, " Requirements for proper

maintenance during storage shall be documented and written

procedures or instructions shall be established.

Items in

storage shall have all covers, caps, plugs, or other closures

intact...The shafts of rotating equipment shall be rotated on a

periodic basis." ANSI N45.2.2 paragraph 6.1.2 states, " Items

shall be placed on pallets or shoring to permit air circulation."

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Valves, Flanges, pipe and fittings were found without cars,

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covers, or protectors to preclude end damage. There were also

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valves, flanges, and fittings on the stored floor loose on the

without cribbing or shoring. Measures have not been established

for the care of items with regard to shelf life conditions,

such as 0-Rings or diaphrams, to prevent degradation.

Requirements

for the periodic turning of rotating shafts had not been implemented

and documented.

ANSI N45.2.2 paragraph 7.5 requires that personnel engaged in

operating material handling equipment, demonstrate satisfactory

ability in operating similar lifting equipment.

Paragraph 8

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requires that personnel qualification records be prepared.

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Personnel engaged in operating material handling equipment did

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not have training records or personnel qualification records.

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Unresolved Item (50-282; 306/81-01-02)

Instrument and Control Procedure, SP-1 Revision 2 Inventory

Control, does not establish QA inspection on QA-1 items which

are unused and returned to storage. The Instrument and Control

Supervisor stated that Quality Assurance does inspect items

which are returned to I&C storage, and that a procedure change

may help clarify QA's role. This item will remain open and

will be reviewed at a subsequent inspection.

c.

Dis 52ssion

During discussions with warehouse and quality assurance / quality

control personnel, it appears that flanges, fittings, nuts and

bolts turned over from construction are classified as safety-

related solely on the basis of heat traceability to test reports.

This fails to take into account such things a N.D.E. requirements,

heat treatments, applicable specifications, quality inputs from

the original purchase order, specific marking requirements, and

vendor quality control on the original purchased item. The

ASME B and PV Code,Section III, requires times and temperatures

for heat treatment and nondestructive examination on material,

depending on class designation, specification and size.

It was

discussed with the licensee during the exit, that before an

item is released and installed in a safety-related system, it

should be evaluated for these type of factors by a documented

engineering evaluation to assure interchangeability, safety,

fit and function. Furthermore, quality assurance should verify

that the correct item was installed.

Since items turned over

from construction were purchased in the early 1970's, some being

manufactured prior to 1970, they should be analyzed the original

purchase order requirements and system designation for present

applicability, prior to installation.

In reviewing microfilm

records, a log designating material turned over from construction,

indicated only " material transfer" in the column marked purchase

order number.

Outside storage areas did not appear to be adequately controlled.

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Most of the items stored outdoors (pipe, fittings, valves, flanges),

were without end caps and some even have standing water on the in-

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side of the tubular products.

5.

Records Program

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The records program was reviewed to ascertain that the licensee is

implementing a program for the control of records that is in confor-

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mance with regulatory requirements, Operational Quality Assurance

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Plan, ANSI N18.7 - 1976 and ANSI N45.2.9 - 1974. Record storage

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controls were reviewed including the system of transferring records

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to the vault. Various records were reviewed for implementation of

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the program and personnel were interviewed concerning storage,

access, and retrievability. The record index was examined and

one-hour fireproof cabinets were checked.

a.

Documentation Reviewed

5 ACD 3.4, Records Management

3 ACD 3.8, Records Management

OQAP 19.0, Quality Assurance Records

b.

Findings

Noncompliance (50-282; 306/81-01-03)

10 CFR 50, Appendix B, Criteria XVII states in part that consist-

ent with applicable regulatory requirements, the applicant shall

establish requirements concerning record retention, such as dura-

tion, location, and assigned responsibility.

In order to meet 10 CFR 50, Appendix B, Criteria XVII the licensee

committed to ANSI N45.2.9 in section 19 of the Operational Quality

Assurance Plan.

ANSI N45.2.9 states in paregc'ph 6.2 that a list shall be generated

designating those personnel who shall have access to the files.

The Operational Quality Assurance Plan requires in paragraph 19.10

that records be stored in at leant one-hour rated fireproof

cabinets.

Contrary to the above, there are no personnel access lists for

records.

Access Control is very lax due to the fact that no access lists

are generated, and records are stored in many locations without

being maintained under appropriate supervision.

The auxillary

building log for 1980 was found on a bookcase, in an open office,

with no controls of any kind.

Furthermore, some records are not stored in fireproof cabinets.

Examples are snubber qualification records and the auxillary

building log mentioned previously.

6.

Audits

The licensee's audit program was reviewed to ascertain whether the

licensee has developed and implemented a program that is in confor-

mance with regulatory requirements and applicable industry guides and

standards. The inspection included verification of the following:

scope of the program is consistent with Technical Specification

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requirements, responsibilities for overall management of the program

have been assigned, and methods for identification and resolution of

audit findings have been defined.

s.

Documentation Reviewed

OQAP 18.0, Corrective Action

OQAP 20.0, Audits

5 ACD 2.2, Internal Audits

3 ACD 2.2, Audits

3 ACD 2.3, Quality Assurance Status Report

b.

Findings

Noncompliance (50-282; 306/81-01-04)

10 CFR 50, Appendix B, Criteria XVIII, states that a comprehen-

sive system of planned and periodic audits shall be carried out

to verify compliance with all aspects of the quality assurance

program and to determine the effectiveness of the program.

Section 20.3 of the OQAP states that required audits shall be

performed each year.

The Operational Quality Assurance Plan commits to ANSI N45.2.12

through ANSI N18.7 in order to meet 10 CFR 50, Appendix B,

Criteria XVIII.

ANSI N45.2.12 states in paragraph 4.3 that a brief pre-audit

conference shall be conducted with cognizant organization

management. At the conclusion of the audit process, a post-

audit conference shall be held with management of the audited

organization to present audit findings and clarify misunder-

standings.

t.NSI N45.2.12 also states in paragraph 4.3 that objective evidence

shall be examined for compliance with quality assurance program

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requirements.

Contrary to the above, the following items of noncompliance were

noted:

(1) A required audit, 3 ACD 9.1, Surveillance Programs, was

not audited since its approval date of March 29, 1979.

(2) Pre and Post audit conferences were not documented as being

held, and Administrative Control Directive 5 ACD 2.2 did not

require mandatory pre and post audit conferences, contrary

to ANSI N45.2.12 requirements.

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(3) Objective evidence was lacking on numerous audits with the

following audits listed as examples: 5 ACD8.2 dated

December 29-31, 1980; 5 ACD 8.4 dated December 17-19,

1980; 5 ACD 14.3 dat<.d October 9, 1980; 5 ACD 3.14 dated

October 21-22, 1980; 5 ACD 7.1 dated November 29, 1979;

5 ACD 8.4 dated November 1,1979; and 5 ACD 8.1 dated

December 29-31, 1980 (reference paragraph c).

c.

Discussion

The objective evidence required on audits was discussed with

the licensee, stressing the fact that objective evidence is

required not only on items of noncompliance but also on satis-

factory response to questions so as to determine the sample,

depth, auditor knowledge, and therefore, scope of the audit.

For example, the licensee audits the N.D.E. procedure,

5 ACD 14.3, once a year. The audit of 5 ACD 14.3 contained

only four questions that resulted in four "yes" answers. The

problems associated with the following audits are typical of

the lack of objective evidence:

5 ACD 3.14, Control of Measuring and Test Equipment

- Audit did not state what equipment was observed.

5 ACD 8.2, Ircientory Control

-Audit did not state what items were inspected for

damage.

-Audit did not state what items were returned to

storage.

-Audit did not state what items were inspected by

the Quality Control Engineer.

5 ACD 8.4, Control of Nonconforming Items

-Audit did not state what discrepancy reports were

reviewed.

-Audit did not state what reject tags were issued.

5 ACD 7.1, Uniform Nuclear Plant Procurement Process

-Audit did not state what change orders were

reviewed.

-Audit did not state what items or services had an

engineering evaluation.

5 ACD 8.1, Receiving Process

-Audit did not indicate what RIF's, Hold tags, Dis-

crepancy Reports or Purchase Orders were reviewed.

Basically, audits should indicate what the auditor reviewed, to

assure compliance with the quality assurance program and to

determine the scope of the audit.

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7.

Document Control Program

The inspector reviewed the program to verify the administrative

controls and implementation of the program were within the require-

ments as setforth in the Prairie Island Operational Quality Assurance

Plan.

a.

Documentation Reviewed

OQAP 8.0, Document Control

OQAP 7.0, Instruction, Procedures and Drawings

5 ACD 4.4, Drawing Control

b.

Findings

No items of noncompliance or deviations were identified.

8.

Design Change / Maintenance Programs

These areas were reviewed to verify that they are being controlled

inaccordancewiththeOperationalQualityAssurancePla9('andthat

previous concerns in these areas had been adegaately resolved,

a.

Documentation Reviewed

5 ACD 6.1, Design Change Control

5 ACD 3.2, Work Request and Work Request Authorization

5 ACD 14.5, Inspection Program

5 ACD 3.1, Prairie Island Plant Organization

5 ACD 3.9, Bypass Control

b.

Findings

Noncompliance (50-282; 306/81-01-05)

10 CFR 50, Appendix B, Criterion V states"... Activities affecting

quality shall be prescribed by documented instructions, procedures

...and shall be accomplished in accordance with the e instructions

procedures, or drawings."

5 ACD 6.1, Design Change Control, revision 7 requires that the

Responsible Engineer shall be responsible for ensuring timely

(three months after installation) close out of design changes

and preparing training material and assuring that affected

plant staff personnel are appropriately trained.

Contrary to the requirement in procedure 5 ACD 6.1, the inspector

found that the following design change packages had not been

closed out three months after installation:

79L519; 80L574;

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79L564.

In addition, for design change 79L564 it was found

that training, regsrding this change, had not been documented

on form 3-3017-10 as required in section 6.3.12 of 3 ACD 4.1.

With regard to the close out of design changes three months

af ter installation, the inspector notes that the plant staf f

has been completing design changes in a timely manner. However,

it appears that delays in close out of design changes are being

encountered in the General Office. These delays appear to

involve drawing revisions,

c.

Discussion

The following concerns were discussed with licensee personnel:

(1) Procedure revisions resulting from Design Changes are not being

issued at the time that the modified system or equipment is re-

turned to service.

In one case, a modification was completed and

put into service and two months later procedure revisions were

issued.

(2) QA/QC is not reviewing the design change packages when they

are closed out.

When the quality section reported to the

PlantSuperintendent Engineering and Radiation Protection he

was responsible for reviewing the completed design change

package.

(3)

Inspection Program procedure 5 ACD 14.5, has not been fully

implemented. This was identified in a licensee internal audit.

(4) The licensee has identified that annunciator response procedures

do not meet the format requirements of ANSI N18.7.

The licensee

has formed a Task Group (No. 80-04) to upgrade the existing an-

nunciator procedures.

Completion of this task is scheduled for

January, 1982.

These items will be reviewed during subsequent NRC inspections.

9.

Fire Fighting Equipment and Systems

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a.

Manual Fire Fighting Equipment

The inspector examined the licensees manual fire fighting equip-

ment including hose and standpipe stations, fire extinguishers,

self contained breathing apparatus, fire fighting protective

clothing and other equipment available for fire fighting. The

equipment availability was reviewed using the commitments contained

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in the Fire Protection Safety Evaluation Report (FPSER) dated

September 6, 1979 with supporting licensee transmittals and re-

quirements contained in the plant technical specifications.

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(1) Documents Reviewed

SP 1606, Monthly Respiratory Protection Check

SP 1183, Monthly Fire Extinguisher / Hose Station Inspection

and Annual Hose Station Inspection

SP 1183a, Containment Fire Extinguisher Placement and Hose

Station Inspection

SP 1203, Fire Hose Hydrostatic Test

SP 1664, Monthly Fire Fighting Equipment Check

FS, Fire Fighting

(2) Findings

No apparent items of noncompliance or deviations were iden-

tified in this area.

,

,

(3) Discussion

The inspector reviewed the results of the surveillance

procedures for manual fire fighting equipment listed below.

Procedure No.

Compeletion Dates of Reviewed Procedures

SP 1606

August 1980, September 1980, October 1980,

November 1980 and December 1980

SP 1183

November 1980 and December 1980

SP 1183a

Unit I: July 1980, September 1980 and

October 1980

Unit II: May 1980

SP 1664

December 1980

The documentation and results of these surveillance pro-

cedures are acceptable. The procedures have been performed

during the required periods of time.

Applicable Technical

Specification surveillance requirements for fire fighting

equipment have been satisfied.

Surveillance procedure SP 1203 is a new procedure.

SP 1203,

concerning fire hose hydrostatic tests, will be implemented

starting this year. Hoses were hydrostatically tested by the

manufacturer when they were purchased.

The inspector verified

documentation of the manufacturer testing on randomly selected

hoses *.hroughout the plant by examining the test results sten-

ciled on the hose jacket.

SP1203 was reviewed for content and

appeared adequate. No results from this surveillance were

examined.

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The inspector examined selected fire fighting equipment

lockers in the following locations during three plant tours.

Auxilliary Building Access Control

Turbine Building Access Control

Unit I Turbine Building 695 foot Level

Breathing Oxygen Bottle Refill Station

The equipment at these locations agreed with the equipment

list in FS, Fire Fighting and satisfied the equipment re-

'

quirements in the FPSER modifications sections 3.1.8, 3.1.10,

3.1.11 and 3.1.15.

Also, during the plant tours, the inspector examined selected

fire extinguisher and hose and standpipe stations. Minor

problems were identified. The licensee was made aware of

these concerns during the exit interview and agreed to examine

them.

b.

Automatic Fire Detection and Suppression Systems

The inspector examined the licensee's automatic fire detection

and suppression systems including the fire water system, cardox

,

system, detection system, pentration fire barriers and fire

doors. These systems were reviewed using information in the

Prairie Island Nuclear Generating Plant Fire Hazards Analysis,

commitments in the FPSER with supporting licensee transmittals

on fire protection and requirements in the plant Technical

Specifications.

(1) Documents Reviewed

SP 1189, Safety-Related Fire Detector Check

SP 1187, Diesel Driven Fire Pump Battery Inspection

PM 3122-1, Diesel Driven Fire Pump Annual Inspection

l

PM 3122-2. Diesel Driven Fire Pump Two Year Inspection

SP 1197, Fire Protection System Header Flush

SP 1660, Winterization of Hydrant and Roof Hose Station.

SP 1053, Monthly Fire Pump Running Test

SP 1524, Diesel Driven Fire Pump Weekly Running Test

SP 1202, Fire Pump Test

SP 1195, Fire Protection System Valve Cycle Checklist

SP 1200, Fire Protection System Supply Valves to Safety-Related

Areas

SP 1196, Fire Protection System Spray and Sprinkler Test

SP 1188, CO System

2

SP 1194, Fire Protection System Cardox (CO ) System Test

2

SP 1192, Safeguard Electrical and Mechanical Penetration

Surveillance Inspection

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SP 1601, Fire Alarm and Emergency Evacuation Test

.

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.

PM 3122-3, Fire Door Mechanical Inspection

5 ACD 9.2, Control of Electrical Penetrations / Openings and

1

Cable Runs

>

D.52, Inutallation Guidelines for the Permanent and Temporary

Sealing of Electrical and Mechanical Openings between

Established Fire Zones

(2) Findings

No apparent items of noncompliance or deviations were iden-

tified in this area.

(3) Discussion

The inspector reviewed the results of the surveillance pro-

cedures for automatic fire detection and suppression systems

and equipment listed below.

Completion Dates

Procedure No.

Frequency

Of Reviewed Procedures

SP 1189

6 Months

January 1980 and July to

September 1980

SP 1187

1 Week

January 1980 through November 1980

PM 3122-1

1 Year

June 1978, June 1979 and May 1980

PM 3122-2

2 Years

June 1978 and May 1980

SP 1197

1 Year

May 1980

'.

SP 1660

1 Year

October 1980

SP 1524

1 Week

October 1980 through December 1980

SP 1202

18 Months

April 1930

SP 1195

1 Year

July 1979 and July 1980

SP 1200

1 Month

January 1980 through December 1980

SP 1188

1 Week

January 1980 through December 1980

SP 1194

18 Months

June 1979

SP 1192

18 Months

June 1979

SP 1601

1 Month

January 1981

Surveillance procedure SP 1196, concerning the spray and

sprinkler systems is a new procedure. A work request was

used the last time that this surveillance was performed.

The inspector reviewed the procedure and results on the

wark request.

The documentation and results of the above referenced surveil-

lance procedures appeared to be acceptable. The procedures

have been performed during the required periods of time.

Ap-

plicable Technical Specification surveillance requirements for

i

fire protections systms are being satisfied.

'

no a plant tour, the inspector examined ten percent of

4

u.

the fire system valves. These valves were found to be in

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the proper position and supervised with wire seals.

Selected

penetration fire barriers and fire doors were examined and

found to be intact and operable. The inspector examined the

fire detection system panel in the control room. This panel

appeared operational.

c.

Procurement Control of Fire Protection Equipment

The inspector examined the licensees fire protection equipment

procurement control. The controls were reviewed using the require-

ments contained in 5 ACD 3.13, Revision 2.

(1) Documents Reviewed

5 ACD 3.13, Fire Preventive Practices

Purchase Orders

(2) Findings

No apparent items of noncompliance or deviation were iden-

tified in this area.

(3) Discussion

The inspector examined the following purchase orders to

verify implementation of 5 ACD 3.13, Section 6.10.1.

Purchase

Fire Protection

Review Completed And

Order No.

Review Specified

Equipment Specs. Listed

MQ 05690

Yes

Yes

MQ 05341

Yes

Yes

MQ 05375

Yes

Yes

M 42033

Yes

Yes

MQ 05202

Yes

Yes

M 07167

Yes

Yes

G 631660*

Yes

Yes

  • Purchase Requisition

The fire protection system procurement control appears to be

adequately implemented.

10.

Fire Protection / Prevention Administrative Controls

'

a.

Fire Emergency and Fire Fighting Procedures

The inspector examined the licensees emergency response procedures

and fire fighting stratagies. The procedures and stratagies were

reviewed using the commitments contained in the FPSER dated

September 6, 1979 with supporting licensee transmittals.

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.

(1) Documents Reviewed

5 ACD 13.3, Fire Preventive Practices

FS, Fire Fighting

F5 Appendix A, Fire Stratagies

(2) Findings

No apparent items of noncompliance or deviations were identified

in this area.

(3) Discussion

The inspector reviewed the fire emergency response procedures

in Section F5. The procedures outline acceptable actions to be

followed by the individual discovering the fire, the control

room personnel, the fire brigade, and other plant personnel in

the event of a fire.

The inspector reviewed the fire stratagies contained in Sec-

tion FS, Appendix A for fire detection zones 1, 4, and 12.

The fire stratagies contain all of the information which the

licensee committed to provide. The stratagies are functionally

organized and appear to provide acceptable fire brigade re-

sponse information when used in conjunction with a modified set

of plant drawings that show zone boundries and detector loca-

tions. A set of all these documents and drawings is on file

in the control room. These documents satisfy the modification

requirements in the FPSER Section 3.1.14.

b.

Ignition Source and Combustible Materials Control

The inspector examined the licensee's administrative controls of

ignition sources and combustible materials. These controls were

reviewed using the commitments contained in the FPSER dated

September 6, 1979 with suppozting licnesee transmittals.

(1) Documents Reviewed

5 ACD 3.13, Fire Preventive Practices

Hot Work / Flammable Material Use Permit

Extended Hot Work / Flammable Material Use Permit

5 ACD 8.5, Housekeeping and Cleanliness

SWI-0&M-3, Nuclear Plant Helper Claaning Assignments

SWI-0&M-9, Control of Combustible Materials at Job Sites

SWI-0&M-12, Housekeeping Zone Designation and Maintenance

(2) Findings

No apparent items of noncompliance or deviations were iden-

tified .

this area.

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(3) Discussion

The inspector reviewed 5 ACD 3.13 and 8.5 and SWI-0&M-3, 9

'

and 12. These documents describe acceptable controls for

the use, storage and movement of combustible materials.

5 ACD 3.13 also deliniates acceptable controls for ignition

sources. The inspector reviewed the following work requests

to verify proper review for fire hazards and, when required,

proper implementation of the hot work / flammable material use

pe rmit .

Work

Fire Hazards

Pe rmit*

Permit

Request No.

Analysis Completed

Required

Completed

D 2461-SE-Q

Yes

No

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D 7367-FP

Yes

No

-

D 7230-SE-Q

Yes

No

-

E 0057-MP

Yes

Yes

Yes

E 0003-DC-Q

Yes

No

-

D 7000-RD-Q

Yes

No

-

E 0053-C0

Yes

No

-

D 6701-ZG-Q

es'

Yes

Yes

D 6702-ZG-Q

Yes

Yes

Yes

D 7189-DE

Yes

No

-

D 6810-SI

Yes

No

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D 6802-MP

Yes

No

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  • Hot Work / Flammable Material Use Permit

During a plant tour the inspector observed acceptable control

of combustible materials and ignition sources including smoking.

Combustibles were stored in designated areas and lockers and

these areas were neat and orderly. Welders had followed

appropriate precautions in performing their work.

c.

Fire Protection Audits And Inspections

The inspector examined the audits and inspections of the licensee's

fire protection and prevention program. These audits and inspec-

tions were reviewed using the commitments contained in the FPSER

dated September 6, 1979 with supporting licensee transmittals and

the plant Technical Specifications.

(1) Documents Reviewed

5 ACD 3.13, Fire Preventive Practices

Prairie Island Nuclear Generating Plant Technical Specifications

QA Audits of 5 ACD 3.13

Fire Issuance Inspection

NSP Corporate Fire Protection Inspection

Kopp and Associates Fire Protection Inspection

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(2) Findings

No apparent items of noncompliance or deviations were

identified in this area.

(3) Discussion

.

The inspector reviewed the QA audits of 5 ACD 3.13 condected

on July 30, 1979 and June 26, 1980. The audits satisfac-

torily examined the provisions in the ACD. Two open items

remain from these audits.

' .

The first open item, QAF No. 31 (December 18, 1978), con-

cerned incomplete fire hazards reviews on work reguests.

The inspector reviewed twelve work requests which all had

completed fire hazards analysis. The second open item,

QAF No. 43 (December 30, 1979) concerned the lack of fire

extinguishers on contractors welding / burning equipment.

Since this item was identified, 5 ACD 3.13 has been revised

and this is no longer a requirement.

The inspector reviewed three audits by offsite organization.

The first audit in February, 1979, by Kopp and Associates,

i

a fire protection consultant, was an indepth analysis of

fire protection at Prairie Island. All recommendations

resulting from the audit were acceptably closed. The

second audit performed by NSP corporate office personnel

in June,1980 and the third audit performed by the licenees

fire insurance company in June, 1980 were acceptably closed.

These audits satisfy the plant Technical Specification re-

quirements, part 6.3.1 for special inspections and audits.

11.

Fire Protection and Prevention Training Program

a.

General Employee and Contractor Training

The inspector examined the licensee's fire protection and

prevention training program for general employees and contrac-

tors. The program was reviewed using the requirements in the

FPSER dated September 6, 1979 with supporting licensee trans-

mittals as modified by the letter from the licensee dated

November 1, 1979.

(1) Documents Reviewed

3 ACD 3.5, Training

5 ACD 3.11, Plant Training Program

Employee Training Records

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(2) Findings

Unresolved Item (50-282; 306/81-01-06)

The letter from the licensee to the Office of Nuclear

Reactor Regulation dated November 1, 1979, concerning fire

protection administrative controls indicated that the fire

protection training program would be implemented through

revision to plant procedures and ACD's.

The revision to

the training program procedures and ACD's was not cor- 4eted

at the time of this inspection. This is considered an

unresolved item and will be examined during a future in-

spection.

No apparent items of noncompliance or deviations were iden-

tified in this area.

(3) Discussion

The inspector reviewed 3 ACD 3.5 and 5 ACD 3.11 and partic-

Ipated in the general employee training for clean and

controlled areas. This program is not in accordance with

the proposed program as described in the letter from the

licensee dated November 1, 1979. Topics that were not

covered completely include fire chemistry and physics and

fire detection systems. This is referred to as Level I

training in the licensee's program description.

The training records for 15 plant employees were reviewed.

All of the employees had received the required training

and documentation was complete.

b.

Fire Brigade Training and Qualifications

The inspector examined the licensee's training and qualifica-

tion program for the fire brigade including classroom training

practice sessions, drills, respiratory protection training, and

medical qualifications. The program was reviewed using the re-

quirements in the FPSER dated September 6, 1979 with supporting

licensee transmittals as modified by the letter from the licensee

dated November 1, 1979.

(1) Documents Reviewed

3 ACD 3.5, Training

5 ACD 3.11, Plant Training Program

Fire Brigade Training and Practice Records

Fire Drill Critique Records

5 ACD 3.13, Fire Preventive Practices (Revisions 1 and 2)

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(2) Findings

Unresolved Item (50-282; 306/81-01-07)

The letter from the licensee to the Office of Nuclear

Reactor Regulation dated November 1, 1979 concerning fire

protection administrative controls indicated that the fire

brigade training program would be implemented through

revision to plant procedures and ACD's.

The revision to

the training program procedures and ACD's was not completed

at the time of this inspection. This is considered an un-

resolved item and will be examined during a future inspection.

No apparent items of noncompliance or deviations were iden-

tified in this area.

I

(3) Discussion

The inspector examined the training records for twenty

percent of the fire brigade members. This included approx-

imately twenty percent of the personnel in the following

!

job categories: shift supervisors, lead plant equipment

and reactor operators, plant equipment and reactor operators,

assistant plant equipment operators and plant attendants.

Records were examined for each individual in the areas of

classroom training and retraining, practice sessions,

medical qualifications and respiratory protection training.

All of the individuals, except one, had received classroom

training in May, 1979. The exception was one new employee

who had received classroom training in June, 1980. No

evidence of the annual retraining (as required in the

letter of November 1, 1979) could be identified. All

of the individuals, except one, had attended a practice

session in October, 1980. The exception was one shift

!

supervisor who was physically unable to attend the session

j

due to a medical problem. There was no identifiable

i

evidence that this individual has been required to partic-

ipate in the alternate training as prescribed in 5 ACD 3.13,

Revision 2.

All of the individuals had received the re-

quired annual medical examination and respiratory training.

The inspector reviewed the training syllabus for the

classroom training and practice sessions. The topics

covered in these training sessions cover an acceptable

spectrum of fire protection principles.

Records for the fire drills and the drill critiques for

drills conducted in 1980 were reviewed. Attendance was

checked for all fire brigade members. The NRC position

on fire drills for each brigade as stated in 10 CFR 50,

Appendix R, paragraph III.I.3.b. is that there should be

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four drills per year at regular intervals not to exceed

three months. Also stated in this paragraph is the NRC

position on fire brigade member participation in drills

which reads as follows: "Each fire brigade member should

participate in each drill, but must participate in at

least two drills per year."

The drill attendance records revealed that 58% of the fire

brigade leaders (shift supervisors) and 14% of the brigade

members (assistant plant equipment operators and plant

attendants) had not participated in the minimum acceptable

member of drills for qualification as a fire brigade

member (two drills per year).

None of the licensed plant

equipment and reactor operators had participated in the

minimum number of drills.

Persons not participating in the minimum number of drills

per year are not considered qualified to satisfy the

minimum staffing requirements for the fire brigade.

12.

Housekeeping / Cleanliness Program

The inspector reviewed the licensee's housekeeping and cleanliness

program to verify that proper administrative controls have been

implemented to assure the quality of safety related systems. The

program was reviewed using the requirements contained in ANSI

N45.2.1 - 1973Property "ANSI code" (as page type) with input value "ANSI</br></br>N45.2.1 - 1973" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. and ANSI N45.2.3 - 1973 as modified by ANSI

N18.7 - 1976Property "ANSI code" (as page type) with input value "ANSI</br></br>N18.7 - 1976" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..

a.

Documents 3eviewed

5 ACD 8.5, Housekeeping and Cleanliness

SWI-0&M-3, Nuclear Plant Helper Cleaning Assignments

SWI-0&M-9, Control of Combustible Materials at Job

Sites

SWI-0&M-12, Housekeeping Zone Designation and

Maintenance

b.

Findings

No items of noncompliance or deviations were identified in this

area.

c.

Discussion

The requirements of ANSI N45.2.3 - 1973 are satisfied by

5 ACD 8.5 and SWI's-0&M-3, 9 and 12.

Zone designations have been

established with cleanliness requirements for each zone.

Cleaning

instructions have been established and icplemented. A requirement

has been established for periodic housekeeping inspections, but

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the inspection procedure has not been implemented. The inspector

indentified minor housekeeping problems in various areas of the

p l a n +. . These items were discussed with the licensee at the exit

interview.

The licensee has not established fluid systems cleanliness pro-

cedures. The requirements of ANSI N45.2.1 - 1973 are implemented

through special instructions on the WR/WRA forms.

13.

Exit Interview

The inspectors met with the licensee representatives (denoted in

paragraph 1) at the conclusion of the inspection on January 8, 1981.

The purpose and scope of the inspection was summarized and the in-

spectors then discussed the enforcement findings in each area.

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