Text

Corporate Mgt Program for Maintaining Occupational Radiation Exposures Alara
	ML20203J211
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	04/21/1986
From:	; NORTHEAST UTILITIES
To:	;
Shared Package
ML20203J178	List: ML20203J174; ML20203J199; ML20203J211; ML20203J233; ML20203J269; ML20203J316;
References
	PROC-860421, NUDOCS 8604300144
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	v • d • e

Policy No 9'

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NEO POLICY STATEMENT CORPORATE ALARA PROGRAM It is Northeast Utilities corporate policy to implement a program to ensure that occupational radiation exposures at its nuclear facilities are kept "as low as reasonably achiev-a bl e" (ALARA).

The program is described in the ALARA Manual and contains management philosophy, objectives and guidelines.

The responsibilities of specific Divisions within Nuclear Engineering and Operations are identified ir. the Manual.

The ALARA program will ensure that:

o Annual exposures (rem) to individual personnel are ALARA o

Annual collective exposures (person-rem) to all personnel at a unit are ALARA o

Design of new units and backfits or modifications (m

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to operating units are done so that based on cost

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benefit evaluations, the collective dose is ALARA o

Maintenance work to operating units is accomplished so that the collective exposure is ALARA o

Individual exposures within various work groups are balanced to be consistent with experience, manpower availability and existing agreements.

The overall responsibility for the Corporate ALARA program lies with the Senior Vice President, Nuclear Engineering and Operations.

Specific responsibility for the development and maintenance of the corporate program lies with the Vice Pres-ident, Nuclear and Environmental Engineering.

All NEO managers and supervisors are responsible for supporting the ALARA pro-gram and for implementing their portions. of the program.

Draft revisions, additions to, and audits of, with the approval of the affected Divisions, are the responsibility of the Vice President, Nuclear and Environmental Engineering.

Final app-royal of all revisions or additions of policy statements rests with the Senior Vice President of Nuclear Engineering and i

Operations.

j W.

G.

Counsil 8604300144 860421 ADOCK 0500 3

Senior Vice President

%DR Nuclear Engineering & Operations.

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03/19/85 Page:

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NEO POLICY STATEMENT RADIATION PROTECTION PROGRAM It is Northeast Utilities' policy to develop, operate, and maintain an effective Radiation Protection Program at its operating nuclear stations to protect radiation workers by ensuring that their exposures are con-trolled to remain within Northeast Utilities' administratively imposed limits and within 10CFR20.

It is the responsibility of all Nuclear Engineering and Operations' management and supervisors to ensure that their staff, their consultants, and their contractors are adequately informed and comply with Northeast Utilities' Radiation Protection Program requirements as stated in station procedures.

Line supervisors and station health physics staff will exercise stop work authority when, in their judgment, actual or potential conditions exist for noncompliance with radiation protection procedures or controls for the job.

It is the responsibility of each radiation worker to be knowledgeable of his/her exposure, to comply with work conditions and procedures applicable to radiation control areas, and to minimize his/her exposure while accomplishing the required work.

Overall responsibility for this program rests with the Senior Vice President of Nuclear Engineering and Operations. The Vice President, Nuclear and Environmental Engineering, is responsible to develop, specify, and maintain Northeast Utilities' health physics standard practices and procedures with input from the Nuclear Operations Division. The Vice President, Nuclear Operations, is responsible to implement these Northeast Utilities health physics standard practices and procedures at the operating stations.

Draft revisions, additions to, and audits of this policy are the respon-sibility of the Vice President, Nuclear and Environmental Engineering.

Final approval of all revisions or additions of policy statements rests with the Senior Vice President, Nuclear Engineering and Operations.

W.'G. Counsil Senior Vice President Nuclear Engineering and Operations L

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NUCIIAR ENGINEERING AND OPERATIONS PROCEDURE 4

NEO 2.05 RADIATION PROTECTION AND MAINTAINING OCCUPATIONAL g

RADIATION EXPOSURES AS LOW AS REASONABLY ACHIEVABLE (ALARA) i e

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' APPROVED (k

4 Seniddce PrWident, Nuclear Engineering and Operations-i REVISION l'

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DATE October 29,'1985 i

CONCURRENCE ha-tk% (' /'sh_ -

Manager, Quality Assurance O

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NUCLEAR ENGINEERING AND OPERATIONS PROCEDURE NEO 2.05

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' RADIATION PROTECTION AND MAINTAINING OCCUPATIONAL l

RADIATION EXPOSURES AS LOW AS REASONABLY ACHIEVABLE (ALARA)

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1.0 PURPOSE i.

The purpose of this procedure is to provide directions for and ~

descriptions of the Northeast Utilities.(NU) Radiation Protection 7

Program to control radiation exposures to be'within NU limits; and the Corporate Management "As Low As Reasonably Achievable" (ALARA)-

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i Program for further reducina occupational radiation exposures as A

necessary to meet-NU Corporate and industry occupational exposure Q2 goals. Minimizing occupational radiation exposures reduces the impact on the health and safety of Company and contractor radiation-workers. Lower tier procedures will be necessary to implement this procedure.

2.0 APPLICABILITY

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This procedure applies to the-Nuclear Engineering and Operations i

(NEO) Group including the Northeast Nuclear Energy Company (NNECO) j and the Connecticut Yankee Atomic Power Company (CYAPCO).

3.0 REFERENCES

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3.1 Code of Federal Regulations, Title 10, Part 20; 10CFR20.-

3.2 Regulatory Guide 8.8, Rev. 3, Information Relevant. to Ensuring-that Occupational Radiation Exposures'at Nuclear Power Stations Will Be ALARA.

i 3.3 Regulatory Guide 8.10, Rev. 1-R, Operating-Philosophy for Maintaining Occupational Radiation Exposures ALARA (Nuclear-l l

Power Reactors).

i 3.4 NEO Policy Statement'No. 9 - Corporate ALARA-Program.

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3.5 NE&O Policy Statement No. 25 - Radiation Protection Program.

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3.6 Institute for Nuclear Power Operations,-(INPO)85-004, Guide-i lines for Radiological Protection at Nuclear Power Stations,-

February 1985.

3.7 INPO 83-012, General Employee Training in Radiological Protec-g i

tion (GET-RP), March 1983.

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NEO 2.05

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Date:10/29/85 i-Page 1 of-9

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5.4 Vice President, Generation Engineering and Construction R$cponsibleforensuring,throughhislinefunctionman[gement,

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that the Radiation Protection Program and the Corporate ALARA Program are implemented at the. stations as they apply to plant.

modifications via backfit-and betterment projects. This includes the specification'of ALARA criteria in project planning (cost-and schedule), equipment design, and materials / equipment g

procurement procedures.

J 5.5 Station Superintendents Responsibl'e for ensuring, through his line function management, the development of station procedures for implementing the Radiation Protection Program and the Corporate ALARA Program at t

the stations.

5.6 Director, Nuclear Engineerina Responsible for maintaining this procedure current.

4 5.7 Mananer, NUSCO Radiological Assessment Branch (RAB) 5.7.1 Responsible for developing L.d maintaining the Radiation Protection Program and the-Corporate ALARA Program.

5.7.2 Responsible for implementing within the Branch-and assisting other disciplines as appropriate in the implementation of the Corporate ALARA Program.-

5.7.3 Responsible, jointly with the Nuclear Training and Station Health Physics Departments, for coordinating and conducting the.NU training and certification-program for Station Health Physics Technicians and Branch Health Physics Staff Supervisors. Also responsible for assisting the Station Health Physics departments'.with the training and screening'of

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contractor Health Physics Technicians.

5.7.4 Responsible for operating and maintaining a Personnel Dosimetry Laboratory.

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5.7.5 Responsible for developing and maintaining a'ccmputer-ized Health Physics Records System.

5.7.6 Responsible for providing the Director, Nuclear'

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Training Department with the' discipline specific content and exam question bank.for the GET-RP program.

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~ Responsible for conducting the General Employee 5.11.3' Training in: radiation protection (GET-RP).

5.12 Director,-Generation Construction Responsible for implementingLthe Corporate ALARA Program j

criteria and goals-into the vendor selection 'and work supervi-sion process associated'withL backfit and betterment. projects.

This includes ensuring that work crew size,-logistics, and time spent in radiation areas are reduced to the minimum necessary levels.

5.13 Director, Generation Projects h

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Responsible for implementing the Corporate ALARA Program criteria and goals into outage planning,. cost and scheduling.

This shall include, from an ALARA standpoint, project prioriti-zation, work scope optimization, and shall include ALARA provisions as job.. prerequisites and not options when outage critical path schedules are being developed.

5.14 Director, Generation Engineering' i

Responsible for implementing the Corporate ALARA Program criteria and goals into equipment design, equipment / materials j

procurement, and installation procedures.

i 5.15 Unit Superintendents t

Responsible for ensuring, through his line function management.

P and interfaces with appropriate Company discipline ~ staff,athat-overall unit operations, outage planning and scheduling, work i

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l scope, and work management.in nuclear unit radiation areas are' consistent with the goals, criteria, and procedures of the Radiation Protection Program and the Corporate ALARA program.

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6.0 INSTRUCTIONS t

6.1

'I The Senior Vice President, NEO,- shall approve.the Corporate' i

ALARA Program and procedures.

The Senior Vice President shall i

approve the use of resources and shall exercise authority to j

ensure that the radiation. exposures are kept ALARA,and that._

f exposures are controlled to remain within NU administrativel'y; j

imposed limits and within 10CFR20.

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6.2 The Manager, RAB, shall, with input'from the Station Health A..t 2

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Physics Department staff, develop, implement, and maintain the.

NU Radiation Protection Program..The procedures in the program.

i Millstone and Haddam Neck Stations.are provided with uniform

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are developed to ensure that all persounel working at the i

l radiation protection controls. The program shall be in compli.

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ALARA CONTROLLED COPY - ISSUE

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' Change No.

i Controlled-Copy No.

Name Date - Sent Date Returned 1.

P. S. Strickland 2.

W.

F.-Fee 3.

4.

E. J. Mroczka 5.

R. T. Harris 6.

G.

L. Johnson i

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R. P..Werner 8.

E. R.

Foster 4

9.

R. H. Graves, CY 10.

H. E. Clow, CY 4

11.

J. O.

Powell, CY l

12.

J. H.

Ferguson, CY 13.

J. O. Crockett 14.

W. D.

Romberg 15.

J. J. Kelley, MP 16.

J. P. Stetz l*

17.

D. W.

Fitts i

18.

J.

P.

Kangley l

19.

E. A. DeBarba 20.

P.

F. Santoro

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21.

A. R. Roby i

22.

R. N. Smart 23.

R. C.

Rodgers 24.

T. E. Quattrochi l

25.

F. C. Libby, Jr.

l 26.

CY Reference l Library 1

(H. E. Clow) 27.

S. M. Turowski 28.

R. A. Crandall 29.

R. K.

Dohetty, MP

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J. G. McHugh 31.

R. F..Lucas, MP 32.

R. E. Michaud i

33.

D.-Ray,'CY 34.

W. D..Bartron, CY r

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35.

R. E. Brown, CY 36.

J. Beauchamp, CY.

37.

B. R. Danielson, CY 4

I & C Supv..

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R. P. Zysk, MP l

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14. Mietlicki, CY

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Change No.

Controlled Copy No.

Name Date Sent

'Date' Returned i

40.

P. Rothen, MP 3

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3333 (R. Zaklukiewicz 42.

I.

L. Haas i

43.

4. Varney, MP

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D. Kross, MP 45.

P. J..Przekop q

46.

R.'Palmari, MP 47.

D. Odland, MP 4R.

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E. Scace, MP jE 49.

J.

F. Smith, MP l

50.

K. Parkinson I

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J. C. Sullivan, MP 52.

F. R. Dacimo, MP L

53.

D. J. Butler, MP 54.

R. Asafaylo,1H?

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G. H. Bouchard, CY 5

56.

C. F. Sears 57.

B.

L. Granados, MP 58.

G.

D. Baston 59.

K. B. Hasting, MP 60.

R.

P. Necci 61.

M. Kupinski j

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L. J. Nadeau l

63.

R. J.

Factora j

64.

G.

R. Doughty i.

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J. S. Keenan,.MP 66.

R. Aft, Nuclear Training j

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K.

L. Burton, MP-3 Ops.

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M. B. Brown, MP-3 I&C j

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C. H. Clement, MP-3

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NORTHEAST UTILITIES CORPORATE MANAGEMENT PROGRAM FOR MAINTAINING OCCUPATIONAL RADIATION EXPOSURES As low As Cf REASONABLY ACHIEVABLE l

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October 3, 1977 The policies and programs in this document.have been reviewed and accepted-by the corporate management of the Northeast Utilities Service Company, Northeast Nuclear Energy Company and the Connecticut Yankee Atomic Power C:mpany.

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D. C. Switzer Q

Executive Vice President NUSCO President NNECO President CYAPCO-O F e

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O NORTHEAST UTILITIES CORPORATE ALARA PROGRAM CONTENTS Revision Date

~2 5/17/82 Part A - Corporate Management Program Part B - Procedures 2

5/17/82 No. 1 Document Control No. 2 ALARA Comparative Cost / Cost - Benefit 5

9/13/85 Evaluation ib. 3 Audits and Appraisals of the Stations' 8

1/24/86 Health Physics Programs 2

9/29/83 No. 4 ALARA Design Reviews 4

9/13/85 No. 5 ALARA Job Reviews No. 6 Implementation and Documentation of.ALARA' 0

5/17/82 Reconnendations No. 7 Review of Plant Design Features and 1

9/13/85 Procedures No. 8 Annual and Outage ALARA Reports 0

7/19/82-C

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M LrrLY1188 SERVICE COMPANY

-~s October 3, 1977 J

To Distribution

D. C. Switzer o !,

sussect Corporate Management Program for Occupational Radiation Exposures In comp"viance with the U.S. NRC regulations, we are implementing a formal ' corporate' management program for maintaining occupational radiation exposures "as low as reasonably achievable" (ALARA). This program provides guidelines for the design of new plants, operating plant design modification and the operating plant procedures. This program will provide the formal mechanism to demonstrate that the company is designing and operating plants such that occupational radiation exposures are ALARA. The program extends current practices in some areas.

The program establishes a Task Force comprised of staff members Erom the operating plants, NUSCO Production Division and NUSCO Engineering Division, during the initial phase of-the program in order to establish accountabil-ity systems.

This program will help in the proper management and control. of occupa-tional exposures. Reducing occupational exposure to valuable trained personnel increases their availability to the company and this benefit can be measured in increased productivity: The program will require that cost-benefit studies be done on new plant design and at the operating plants. This can translate into expenditures to reduce occupational ex-posure such as, changing equipment design or layout, more radiation shielding, chemical cleaning of certain systems, changing work pro-cedures and even personnel training.

This program is being implemented because it is cost-effective for the utilization of manpower and the operation of our plants. There have been no observable health effects on any occupationally exposed individual

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for operations that are in compliance with the radiation criteria in 10CFR20.

Implementation of such a program is timely, necessary and will benefit Northeast Utilities.

W. F. Fee W. Greten R. A. Evans V. E. Peoppelmeier J. P. Cagnetta J. Kufel R. P. Werner E. J. Ferland H. R. Nims R. Graves

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I NORTHEAST UTILITIES CORPORATE MANAGEMENT PROGRAM FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS l

REASONABLY ACHIEVABLE PART A CORPORATE MANAGEMENT PROGRAM Reviews Completed And Comments Resolved M'AA Manager, Radid.ogical-Assessment Branch, NUSCO Procedure A prov

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IN6L Senior Vice President, Nuclear ' Engineering & 0pers.

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NUSCO,~ NNECO,_CYAPCO S /7 /82.

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Introduction.

4 There is increasing awareness of the need to reduce the exposures j

from man-made radiation to members of the general public and occupa.

tional workers. 'This awareness is; expressed in the p'ublic_ forum as a general concern about all aspects of radiation released either routinely or inadvertently. from operating nuclear power plants,.

irrespective of the magnitude of'the-release. This awareness'is, also expressed by federal and state regulatory agencies in the form of more stringent radiation exposure criteria. This is a conserva--

tive approach even though no health effects have :been observed by ;

-j operating within the present radiation protection; criteria-contained in 10CFR20.

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In the case of concern for_the radiation exposure to the general' public it is the U. S. Nuclear Regulatory Commission's (NRC) issuance of Appendix I to 10CFR50'(May 1975) which provides' numerical' guides for design objectives to meet the "as low ~as reasonably achievable" (ALARA) criterion for radioactive material in.

light water reactor effluents. This has resulted-in extensive-and costly modifications in the ~ radiation' waste treatment systems of

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operating plants and the installation of similar; systems in new i.

plant designs at Northeast Utilities.

In: addition the U. S. Environ-mental Protection-Agency (EPA) has issued 40CFR190 (January 1977) which has reduced the original limitsL(10CFR20) on. maximum allowable i

exposures to the general public from facilities operating on the l

uranium fuel cycle by a factor of twenty'.

Both of-these new I

criteria have caused our present operating plants :and newl plants. to j

be designed with elaborate and demonstrable cost-effective waste treatment systems. Thus, in the casejof~ radiation exposure-to.the general public, Northeast Utilities has taken all possible. measures to keep it "as low as reasonably achievable"; We have succeeded in-i reducing the population radiation exposure from a few hundred 1

I person-res per year to less than 10 to.20 > person-rem per year per.

unit.

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The NRC has expressed their concern by theiissuance of-.two Regula-l tory Guides, 8.8 (March 1977) and 8.10 (September;1975) which j

require the development of a management and operating philosophy;to' l

keep occupational radiation exposures AIARA.

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The intent of this program is to. formalize a corporate management-l' philosophy and to' document and extend,'if necessary, programs at-

,,1 Northeast Utilities' operating.and planned plants to ensure that occupational radiation exposure is kept ALARA. Our corporate '

l commitment to nuclear power requires that weJaddress~this: issue positively.

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Management Philosoph7 and Commitment It is management's intention to-ensure that'all aspects of nuclear

_ plant design and nuclear power plant : operations: be co.nducted.in a-manner such that-occupational exposures are "as low as. reasonably 1 3

achievable" (ALARA).

If it.can be shownLin a reasonable fashion '

I that the radiation exposure ;is "truly unavoidable" or the " cost" of 3

an additional reduction in radiation exposure is. unreasonable,.then-

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it is by definition ALARA. ' It should, however,.be demonstrable that -

supervisory practices,' planning or training, radiation protection practices or the design of our new plants are' net contributing-factorsEto unnecessary radiation exposure. Maintaining occupttional radiation exposure ALARA is a. management. commitment.thatidesignated individuals within the company are charged.with the responsibility of implementing. However, it should.tne apparent that:in order to i

achieve ALARA successfully good radiation exposure control practices i

must be maintained at all employee levels.

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With this commitment in mind a more formal management ALARA program has been defined for use throughout the Northeast __ Utilities Company System.

It'must be recognized that_ future plant designs, operating plant design modifications and,present operating plant-experience are inextricably intertwined. The feedback loop of radiation exposure information from operating plants into plant.

design mast be used. All divisions of the Company must work-together in order to achieve theseLobjectives and: fulfill our s.

commitment.

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Occupational Radiation Exposure ALARA Program A.

Objectives i

In accordance with corporate ' management's commitment to keep occupational' exposures ALARA a basic program.isLoutlined below.

The objectives of this program are:

(1) To maintain the annual dose (rea) to' individual personnelf ALARA.

(2) To maintain the1 annual collective' dose (person-res) to'all:

' personnel at' a unit ALARA (a unit is either a unit.under.

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design or an operating unit).

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(3) To design new units so.that the annua 1' collective dose to all personnel is ALARA.

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(4) To balance individuals exposure within the various. work groups consistant with experience, manpower and union agreement limitations.

B.

Guidelines j

i To attain these objectives a,t operating plants and in new plant-j design, the following guidelines'are provided:

1 (1) The maximum annual radiation exposure to'any'individualtat the plant should not exceed'5 R.en'..Under special circum-stances and with the approval of upper plant management,'-

this exposure level can be exceeded within the limits established by 10CFR20.

(2) As a decision making tool, to determine if a particular job or design is AIARA, a cost-benefit evaluation should-be done.

Although a cost-benefit evaluation-can be -done on all jobs or designs, it should be done on those-for which the 2

I exposure is either estimated or known from past experience to contribute a significant fraction of the total annual collective exposure.

In many cases, occupational exposure is not-the.only-ites of concern. Equipment and personnel safety as well as operational: reliability should;also be' considered.

i (3) At operating plants, an exposure measurement and recording system should be used for each: individual receiving'an i

exposure that requires a Radiation' Work Permit. The-

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source (s) of the exposure as' recorded by'the'perscnnel i

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dosimetry system should be ' identified in detail., Details s

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.Page A-4 required for the records system should include _the job,

-1 category; the major pl. ant' system," the component within the system and the type of work.

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' A computer based system is used to perform Radiation Work Permit exposure data collation and correlation routines for pre and post job ALARA evaluations.

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Implementation The Corporate ALARA. Program'is implemented by the _fcllowing major organizational groups:

The two operating sites NUSCO Ge'neration Engineering and Construction NUSCO Nuclear-and. Environmental Engineering A detailed description of the responsibilities of the different groups-is given below.

A.

Operating Sites (Millstone, Haddam Neck)

The Station and Station Services Superintendents are respon--

sible for:

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(1) Writing procedures for the ALARA program at the plant to ensure that:

(a) All plant personnel, contractors ~and visitors comply with the ALARA program guidelines.

(b) Suitable. authority is delegated'to the appropriate plant personnel to ensure compliance with the ALARA s_

program.

(c) Suitable advance planning and special training is completed prior to all-plant-jobs that could result -

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in significant radiation exposures to ensure ALARA.

(d) Prior to a refueling and/or a major maintenance shutdown a review of the potential for radiation exposures is made and technical guidance and planning for keeping the exposures ALARA is'provided.

(e) Corrective actions are taken when the attainment of 4

specific objectives are jeopardized.

(2) Assisting,in the development and maintenance of an occupa-tional exposure data accounting system-to identify the -

sources in the, detail required by the ALARA program and provide suitable and timely information to-the department supervisors to further assist them in the. decision making process of exposure management.

(3) Ensuring that adequate personnel, facilities, instrumenta-tion and equipment are available to achieve an effective ALARA program.

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(4) Ensuring that all Unit and Station Engineering personnel incorporate ALARA consideration _into the design and

-e selection of new facilities'and equipment as well as all Plant Design Change Requests (PDCR's).

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Rev. 2 Date 4/82

'Page.A-6 (5) Participating in special programs and studies 'for identi-fying the locations, operations and conditions which have.

a potential for causing or have caused significant radiation exposures to personnel.

(6) Submitting an annual report to the NUSCO Radiological-Assessment' Branch summarizing the-activities undertaken at the Stations as part of the ALARA program.

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NUSCO, Nuclear and Environmental Engineering Department, Radiological Assessment Branch The Manager of the Radiological Assessment-Branc,h has the respon-f sibility.for:

(1) Ensuring that an effective measurement system is estab--

lished and used to determine the degree of' success achieved by.the various company organization groups with regard to the ALARA goals and objectives.

l (2)'- Providing technical guidance and assistance to all person-

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j nel involved with the ALARA program.

(3) Developing additional guidelines, if necessary, to further implement ALARA goals or new NRC or EPA criteria.

(4) Assuring that occupational exposures in future plant designs and in operating plant design modifications are in accordance with the ALARA program..This includes:

(a) Writing. implementing procedures for the Nuclear Engineering and Operations ALARA program.

(b) Reviewing the Millstone Unit 3 design to ensure that O

corporate ALARA policies and programs are adequately

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implemented.

e (c) Participating in the revie,w of operating plant design modifications to-ensure that exposures will be ALARA.

(d) Ensuring that sufficient' authority has b'een delegated' for providing procedures a'nd practices by which the goals and objectives of the ATARA program may 'be achieved.

(e) Ensuring that the resources needed to achieve ALARA are available.

(f) Ensur,ing that corrective actions are taken when the attainment of specific objectives are jeopardized.

(5) Assisting the operating stations with development and operation of an occupational exposure accounting system.

This includes:

(a) A system for recording and retrieving data to account.

for the radiation exposure in the detail required by the ALARA program.

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i (b) Instituting and directing special studies t'o identify' j

the sources of exposure in the operating plant, their-relative magnitudes and their behavior with the-

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plant's operating; history.

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-Rev.12-Date 4/82, Page A-8

<- O (6) Analyzing the operating plants exposure-data for the purposes. of:

(a) Using'this'information to improve _the design of new plants and-the design of the operating plants.

(b) Providing a feedback system to.the operating plant personnel on their exposure data for planning pur-poses and for the implementation of. future ALARA program activities.

(7) Coordinating and preparing an annual raport to management

.that includes an account on the progress of the ALARA program in all company divisions,' the' major highlights and, if necessary, recommendations for future actions.

(8); Performing audits of the Health Physics and ALARA programs to ensure compliance with the regulations,. guidelines and procedures.

(9) Develop or improve sys-rograms and procedures to, more effectively implems.

.porate ALARA goals and objectives.

1 C.

The Director of Generation Engineering and the Director of Generation Construction,s' hall ensure that 4

Plant Design Change Requests, New facility designs, I

Backfit projects, Equipment Selection, incorporate ALARA design and installation review considera-tions. Vendor selection and contract and. vendor procedures should implement Corporate ALARA objectivesLand procedures.

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PART'B CORPORATE MANAGEMENT ALARA PROGRAM PROCEDURES

\\

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' NORTHEAST UTILITIES COR'PORATE MANAGEMENT PROGRAM FOR

, MAINTAINING OCCUPATIONAL EXPOSURES

~AS LOW AS REASONABLY ACHIEVABLE PART-B

~

PROCEDURE #1 DOCUMENT CONTROL' l

Reviews Completed and Comments Resolved Manager, Radiological Assessment Branch, NUSCO Procedure Approved' e

$'?k)t Senior Vice President Nuclear Eng. & Opers.,

NUSCO, NNECO, CYAPCO G// 7/9'2.

Date O

4

\\

Rev. 2 Date 4/82

/~'s Page B/1-1 Nj' 1.0 PURPOSE To' maintain control,of the text of the Corporate Management. Program (Part A) and the procedures (Part B); ensure standard format, adequate review and approval of changes; ensure controlled distribution.

~

2.0 APPLICABILITY Manager Radiological Assessment NUSC0;.all Controlled Copy Holders; and management personnel interested in making additions / changes.

3.0 FEIERENCES None.

l 4.0 DEFINITIONS None.

i 5.0 RESPONSIBILITIES 5.1 Senior Vice President, Nuclear Engineering'& Operations, NUSCO, i

~'

NNECO & CYAPCO: Approve all new procedures ~or changes.

O 5.2 Manager, Radiological Assessment, NUSCO: Maintain master copy of Corporate ALARA program document; initiate / coordinate all changes; issue controlled copies.

6.0 PREREQUISITES None.

7.0 PRECAUTIONS None.

8.0 INSTRUCTIONS 8.1 Procedure Format 8.1.1 All procedures shall have the following format:

1.0 PURPOSE 2.0 APPLICABILITY

3.0 REFERENCES

4.0 DEFINITIONS 5.0 RESPONSIBILITIES 6.0 PREREQUISITES 7.0 PRECAUTIONS 8.0 INSTRUCTIONS Ci 9.0 ACCEPTANCE CRITERIA 10.0 RECORD KEEPINO

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11.0 CHECK-OFF LISTS / FIGURES /ATTACHNENTS c

M

.x.

{

.Rev.' 2 Date 4/82

(

Page B/1-2:

8.1.2-

- All section and subsection numbering shall'be numerical.

1-8.1.3 All sections sp,ecified in.8.1.1 shall be included in a procedure.

If there 'is no content in. a' section the ' word "None shall 4

i appear.

8.2.' ADDITIONS / CHANGES ~

[

8.2.1 Management personnel.in NUSCO or the' plants can initiate"an addition / change in the program and procedures.- They should.

4 contact.the Manager, Radiological Assessment,'NUSCO, and work i

out the details.

8.2.2 Additions / changes should be circulated to' appropriate NUSCO and'

[

plant management personnel'for review prior to issuance. The I

Manager,' Radiological Assessment will be responsible to insure i

that this is accomplished. All comments will be considered and j

a' final version issued.

8.2.3 The Manager, Radiological Assessment will sign the title sheet of each procedure to indicate that management reviews were.-

i performed and comments were resolved.

1 8.2.4 The Senior Vice President, Nuclear-Engineering and Operations, j

NUSCO, NNECO and CYAPCO will approve all procedures and revisions thereto.

i 8.3 DISTRIBUTION 8.3.1 The Manager, Radiological Assessment'will distribute controlled j

copies'and maintain a list of holders. 'The transmittal and-l acknowledgement with receipt form is shown in Figure 1.

He

~

will maintain a log of these transactions as shownfin Figure'2.

4 8.3.2 An Up-To-Date Table of Contents will be distributed with each l

addition or change.

8.3.3 Controlled copy holders should sign and' return the transmittal'

~

.c sheet within-thirty (30) days.

j 8.3.4 The Manager, Ra'diological Assessment.will maintain the Master i.

Copy and a copy of the changes thereto.

l-i.

j 9.0 ACCEPTANCE CRITERIA f

None.

l' j

10.

RECORD KEEPING i

The Manager, Radiological Assessment will maintain a record of.all' revisions of the ALARA document and theilist.of controlled copye

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holders.

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Rev. 2 Date 4/82 Page B/1-3 11.0 CHECK-OFF LISTS / FIGURES / ATTACHMENTS Figure 1. Program / Procedure Change Notice Figure 2. Controlled Copy - Issue Log 4

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1

Rev. 2 Date 4/82 FIGURE 1 SUBJECT PROGRAM /PRdCEDURE CHANGE NOTICE DOCUMENT: Northeast Utilities Corporate Management Program -For Maintaining Occupational Radiation Exposure AS LOW AS REASONABLY ACHIEVABLE.

TO:

NAME CONTROLLED COPY NO.

DATE Please insert into your controlled copy the following change (s). Also destroy all superseded versions.

INSERT DESTROY SECTION/ PROCEDURE NO.

REV NO.

SECTION/ PROCEDURE NO.

REV. NO.

b Upon completion, please sign below and return this change notice within thirty (30) days to R. C. Rodgers, Berlin, W-133.

Signature Date dip C

m.+-

b

1 4

0

' u NORTHEAST UTILITIES CORPORATE tuNAGEMENT PROGRAN FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE PART B I

PROCEDURE #2 ALARA COMPARATIVE COST / COST BENEFIT EVALUATIONS t

i i

4 Reviews Completed and Comments Resolved j

v Manager, Radiological W sessment Branch, NUSCO l

Procedure Approved SeniobJ&ce Presiinnt, Nuclear Eng. & Opers.,

NUSCO, NNECO, CYAPCO' bb~

lb. l% % f Date V

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.s.

1.0 PURPOSE i

To provide a method for performing Cost Benefit / Comparative Cost evaluations using engineering econceic models to provide a decision basis for determining the need for changes in equipment, systes' design, manpower, operating procedures, etc., in order to keep exposures ALARA. To ensure that ALARA considerations are merged-into the overall cost-benefit /coepsrative cost analysis that are a j

necessary part of an engineeri:23 project evaluation.

i 2.0 APPLICABILITY i

To all NUSCO NE&O engineers, plant staff engineers, health' physics staff, ALARA Coordinators, etc., involved in plant design changes, new plant equipment design, plant procedure changes and plant operations whenever the need for an ALARA cost-benefit / comparative i

l cost analysis is identified.

i 4

3.0 REFERENCES

i 3.1 NU Engineering Econceics Text.

3.2 The Monetary Value of the Collective Dose Equivalent' Unit (Person-Rem), R. C. Rodgers. Health Physics Society Annual Meeting, June 18-23, 1978.

3.3 Update

Monetary Value of the Collective Dose Equivalent Unit for

]

Occupational Exposure, J. J. LaPlatney, June 1982.

I 4.0 DEFINITIONS i

None 5.0 RESPONSIBILITIES i

5.1 The project engineer or originator of a PDCR, procedure change, equipment design, etc. as specified in Section 2.0 above is j

responsible to perform an ALARA cost-benefit / comparative cost l

analysis if occupational esposure is involved, i

5.2 The NUSCO Radiological Assessment Branch (RAB) will be responsible i{

to assist the project engineer or originator (itse 5.1) in performing these evaluations for all new equipment designs performed at NUSCO engineering. They will be available 'to perform or assist' in such evaluations performed at the plants.

5.3 All ALARA Cost Benefit / Comparative Cost evaluations should be j

independently reviewed by other NUSC0 ~ or plant personnel, as j

appropriate. Evaluations that involve jobs whose esposure i,s estimated as ten person-res or more must be reviewed by RAB

}

personnel to ensure completenesa of the measures considered and that the items in Section 7.1 have been properly addressed.

L L

~.

Rev.:5 Date 8/85-Page B/2-2 D

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6.0 PREREQUISITES Supporting informati9n as necessary on person-res; man-hours; and

_l' capital, operating, maintenance and equipment _ salvage costs.

7.0 PRECAUTIONS j

7.1 When performing ALARA cost. bene' fit or comparative cost evaluations,.

other factors besides balancing occupational radiation exposure and I..

associated capital and operating costs must be considered. These-factors include:

i f

o Personnel safety o

Equipment reliability NU corporate and industry goals for reducing the total-o cumulative exposure for the operating unit or the NU system to

=

comparable like plants.

I This procedure does not address safety and reliability, although their input is, in some instances, critical. Expressing safety and reliability in dollars, if possible, will be up to the individua,1, users of this procedure.

For jobs that have the potential or probability of significantly l

increasing individual unit or system exposure, using the dollar j

value of a person-rem determination, as described in this procedure, j

night no be adequate. Rather,' efforts should be made to ensure that corporate goals are achieved and to ensure that NU plant i

collective exposures are reasonably comparable to like plants'in the l

a industry.

-l 3

j 7.2 If assistanc'e is needed in performing these analyses, contact the Manager, Radiological Assessment Branch, NUSCO.

~

I 7.3 Obtain capital investment carrying charges data from Capacity ll Planning, NUSCO.

7.4 Obtain current interest rate data from the Radiological Assessment l

Branch, NUSCO.

7.5 ALARA Cost Benefit /C'osparative Cost evaluations will not include refueling outage critical path expenses such as replacement power cost.

I 8.0 INSTRUCTIONS

)

8.1 Comparative Cost / Cost Benefit Analysis For Capital Expenditures j

If the job for which the comparative cost / cost benefit evaluation is being made is estimated as involving an exposure 'of 10 person-res or greater,'then NUSCO RAB shall-be contacted to perform an independent review of the evaluation.

i t

y.

Rev. 5 Date 8/85-Page B/2-3' 8.2 This analysis requires a year by year cumulative present worth determination to evaluate the fiscal consequence of the expenditure ~

in both the short and'long term.

8.2.1 Table 1 lists the data requirements for an ALARA year by year cumulative present worth determination..This i

determination provides the basis for both comparative cost i

and cost benefit analynis.

4 A cost benefit analysis is made by a ' sin'gle cumulative present worth deteunination which compares the revenue l

requirements for making a. proposed change to the revenue requirements for the present situation, q

A comparative cost analysis requires that cumulative present worth determinations be made for several ~

alternatives.

(

8.2.2 Table 2 gives the dollar value of a person-rem and shall be used for all ALARA cost benefit and' comparative cost i

analysis.

8.2.3 Table 3 provides a worksheet for cumulative present worth calculations. Listed below is a column by column explanation of how to use the worksheet:

I Column A - Year: Enter the calendar year starting with-the in-service date. The number of years used is a variable but twenty,may be cons.idered an upper limit.

I Column B - Carryina Charnes: These are calculated on a l

year by year basis by the Financial Carrying Charges Model i

which is available from Engineering Computer Services.

5 L

Column C - Property Tax:.This' revenue-requirement is l

usually a constant value for the life of the component.

Plant Accounting, Property Tax Section, provides this j

information.

f Column D - Operations and Maintenance: The yearly cost I

for operation and. maintenance, this : includes labor (which

~

must be escalated), person-res expended and critical path time. Escalation rates are available from Capacity Planning.

i=

f l

Column E - Total Revenue Required: This is.the sum of 1

Columns B, C and D and represents the total cost'of the-item in the year of interest.

Column F - Yearly Revenue Required, No Change: The total l

yearly cost for the existing installation which includes

. i l

labor, person-res and ' critical path time. Costs should be escalated as appropriate.

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I Rev. 5' l

Date 8/85-i Page B/2-4J l

Column G - Revenue Requirement Advantane of the Chanae:

This is calculated by subtracting Column E from Column.F; if the value of Column G is positiye, the proposal is' cost' F

effective for that year.

Column H - Present Worth of Revenue Requirement Advantaae:

The present worth of the value in Column G is entered here.

1

' Column I - Cumulative Present Worth: This is the cumulative total of the values in Column H.

'A positive i

value indicates the proposal is cost beneficial.

1 Note:

An investment of marginal value will initially

{

be negative before it becomes positive.

If the

)

l cumulative present worth is not positive within l

ten years, the investment will be' considered too costly.

i 8.3 Comparative Cost / Cost Benefit Analysis For Operatina Expenditures I

This analysis requires a present value or an annual level premium j-determination. The choice is dependent on the problem.

l 8.3.1 Table 4 shows an example of a present value'(PV) analysis.

i For annually recurring situations use the Uniform Series-Present Worth Factor (USPWF) from Attachment 1.

For a one time situation at time zero use the-dollar value as is.

t i

l 8.3.2 Table 5 shows an example of an annual level premium (ALP) analysis. For annually recurring situations use the dollar / year value as is.

If a one* time situation at' time zero, multiply the dollar / year value by the Uniform Series j

Capital Recovery Factor (U8CRF) from Attachment 1' l

9.0 ACCEPTANCE CRITERIA i

9.1 If the costs and benefits (or comparative costs) are more than j

10 percent apart the decision should be made as indicated unless Section 7.1 items are paramount.

9.2 If the ALARA cost and benefits (or comparative costs) are within 10 percent of each other then the ALARA factors should be implemented unless Section 7.1 items override.

j 10.0 RECORD XEEPING l

The results of the Comparative Cost / Cost Benefit' analysis should be,

included in the project file, if performed as part of a Project lO Assignment.

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Rev. 5 Date 8/85 Page B/2-5 11.0 CHECK-OFF LISTS / FIGURES / ATTACHMENTS

. ALARA Cumulative Present Worth Determination - Typical Table 1.

Parameters i

Table 2.. Dollar Value of a Person-Rem Table 3.

Cumulative Present Worth Determination Table 4.

Present Value Analysis Table 5.

Annual Level Premium Analysis.

Northeast Utilities Engineering Economics Tables I

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_y Rev. 5 Date 8/85 Page B/2-6 TABLE 1 ALARA CUMULATIVE PRESENT WORTH DETERMINATION - TYPICAL PARAMETERS 1.

Capital Cost 2.

Operating Cost 3.

Maintenance Cost 4.

Property Tax 5.

Man-Heurs Seved 6.

Man-Hours Increased 7.

Person-Rem Saved 8.

Person-Res Increased 9.

Equipment Salvage 10.

Current Intesest Rate i

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D 9

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1 Rev. S Date 8/85 Page-B/2-7

-TABLE 2 DOLLAR VALUES OF A' PERSON-REN (Per Reference 3.3) i

~

For Nuclear power plant design and operation when ALARA cost-benefit l

evaluations are done per 10 CFR 20.

1 i

A.

$1.000 Per Person-Res i

l This monetary value of the Collective Dose Equivalent Unit applies for the majority of cost / benefit analysis except.as described j

below.

It is to be used for both company and contractor personnel 1,

person-rem.

1 B.

For those jobs (most notably, maior steam generator, work) that require many workers be used because of individual exposure limitations, a job-specific dollar value of a person-ren will be calculated.

I by Radiological Assessment Branch personnel using the formula i

described below.

j Special (Hinh Work Area Dose Rate) Cases

{

~Work in high dose rate areas can result in workers reaching'their exposure limit before completing the job. This results in extra workers being required to complete the job and the additional costs to retain them. These costs can be calculated using the following equation:

Dollars /

= $228.00 + _ $1.213

+ Job-specific costs (NEW)/TJEE Person-Ree extra worker extra worker Extra Worker Independent Costs, i.e., adverse health l

Where $228.00

=

i effects, insurance, loss of lifetime earnings.-

$1,213.00 =

Extra Worker Dependent Costs, i.e., unproductive time-due to health physics training, administrative processing worker orientation, etc.

i

~ '

Total Job Exposure Estimate'which is obtained by TJEE

=

multiplying the job's total work hours by the average work area dose rate (R/hr)..

4 Number of Extra Workers. This is calculated in a j

NEW

=

multistep process. First calculate the total number l

of workers required to perform the' job by dividing i

the total exposure by the average amount of remaining I

allowable exposure for the quarter per worker.

l Total workers = (total exposure)/(average remaining l

l exposure per worker)..Then estinste the number-of ~

l workers the' Job would 'equire if it;were not

,j r

performed in a radiation area. The number of extra

[

workers is the difference between the two.

a l

.~...____._.._a___.___._,_

.. _. _, ~. _

Rev. 5 Date 8/85 Page B/2-8 The sum of such items as mock-up training expenses, l

Job-Specific

=

Costs Per guaranteed minimum work times per labor agreements, Worker additional vendor training fees, etc.

j C.

Inherent in the values and methods provided above, is the assumption that we do not hire additional permanent company personnel for the purpose of maintaining a station work group's exposure within allowable limits.

If a particular job would result in permanent employees reaching their exposure lLait, then contractors would be hired for the job. Hence, the above values are all based en the cost of hiring additional contractor personnel.

Should permanent company employees ever be hired for the purpose of maintaining exposure within limits, then a special calculation should be performed to determine the dollar value of a person-res for company personnel.

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Rev. 5 Date s/8.

Page B/2-9 TABLE 3 CIMULATIVE PRESElfr idORTN DETERMINATION A

B C

D E

F G

N I

YEARLY REVENUE REQUIREENT YEARLY REVENUE PRESENT PROPOSED CNANGE REVENUE REQUIREENT '

idORTN OF OPERATIONS TOTAL REQUIREENTS ADVANTAGE REVENUE CUMULATIVE CARRYING PEOPERTY AND REVENUE NO OF REQUIREMENT PRESENT YEAR

CNARGE TAX MAINTENANCE REQUIRED CNANGE CNANGE' ADVANTAGE

%dORTN (1)

(2)

(3)-

(4)

(5)

,y

_m,

.(6) i (7)

(a)

(9)

(10)

(11)

(12)

The museer of years analyzed is situation dependent based on how fast the cumulative present worth becomes a -

positive number. Very rarely should it be necessary to analyze more than 12 years.

+

g, A

1 3

.. - ~

Rev. 5 Date 8/85 Page B/2-10 TABLE 4 PRESENT VALUE ANAI,YSIS BENEFIT COST (a) Person-Rem Saved ( } ($)

(a) Person-Rem IncreaseII) ($)

(b) Man-Hours Saved (I) ($)

(b) Man-Hours Increased (I) ($)

(c) Equipment Salvage ($)

(c) Annual Operating and Maintenance Cost-($)

(d) Other Taxes (d) Property Tax ($)

etc.

(e) Other Taxes etc.

i F

Total PV Benefit

($)

Total PV Cost

($)

~

O (1) If a one time situation at time zero use $ value as is.

If it recurs annually for next n years, multiply $ value by USFW where a is the remaining life of the equipment, in years, or that shown in Attachment 1 for specific equipment.

t e

C

Rev.' 5 Date 8/85 Page B/2-11 t

TABLE 5 ANNUAL LEVEL PREMIUM ANALYSIS BENEFIT COST (a) Person-Rem Saved (I) ($/yr.)

(a) Person-Rem Increase (I) ($/yr.)

(b) Man-Hours Saved (I) ($/yr.)

(b) Man-Hours Increased ( } ($/yr.)

(c) Annual Operating (I) and Maintenance Cost ($/yr.)

(d) Property Tax ($/yr.)

etc.

Tots). ALP Benefit ($/ year)

Total ALP Cost ($/yedr)

(1)

If ic is annually recurring use $/yr. value as is.

If a one time O

situation at time zero, multiply $/yr, by USCRF where n is the re-r maining life of the equipment, in years, or that from Attechnent 1.

F S

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Rev. 5 Date 8/85 Page B/2-11 i

ANNUAL LEVEL PREMIIDt ANALYSIS BENEFIT

C_0_ST, 4

(a) Person-Rem Saved ( ) ($/yr.)

(a) Persen-Rea Increase (I) ($/yr.)

(b) Man-Hours SavedII) ($/yr.)

(b) Man-Hours-Increased ( } ($/yr.)

(c) Annual Operating (I) and Maintenance Cost ($/yr.)

(d) Property Tax ($/yr.)

etc.

Total ALP Benefit ($/ year)

Total ALP Cost ($/ yea _r) 1 (1) If it is annually recurring use $/yr. value as is.

If a one time situation at time zero, multiply $/yr by USCRF where a is the're-maining life of the equipment, in years, or that from Attachment 1.

e a

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_.-.~.__..-.-,.__.-~-~_..,.__....-._..._.-.:_,....-__..:____..,..a

I Rev. 5 Date 8/85 Page B/2-12 ATTACHNENT 1 NORTHEAST UTILITIES ENGINEERING ECONOMICS TABLES O

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Rev. 5 1

8/85 Page R/2-t3 ESTIMATED AVERACE USEFUL LIVES FOR BOOK AND TAX PURPOSES E

Y NET SALVACE RATES ELECTRIC PLANT, Average Average Net Life-Years Life-Years Salvage (Tax Purposesl (Book Purposes)

(%)

Ac count

' STEAM PRODUCTION PLANT 311 - Structures and Improvements 22.5 (10)

(5) 312 - Boiler Plant Equipment 22.5 0

314 - Turbo-Generator Units 22.5 O

315 - Accessory Electric Equipment 22.5 O

316 - Miscellaneous Power Plant Equipment 22.5 NUCLEAR PRODUCTION PLANT 321 - Structures and Improvements 16 322 - Reactor Plant Equipment 16 323 - Turbo-Generator Units 16 324 - Accessory Electric Equipment 16 325 - Miscellsaeous Power Plant Equipment 16 MDRAULIC PRODUCTION PLANT 331 - Structures and Improvements 40 (l'D) w-332 - Reservoirs, Dass and Waterways 40 (10) 333 - Waterwheels. Turbines and Gensrators 40 (5)

O 334 - Accessory Electric Equipment 40 O

335 - Miscellaneous Power Plant Equipment 40 336 - Roads. Railroads and Bridges 40 O

OTHER PRODUCTION PLANT 341 - Structures and Improvements 22.5 O

342 - Fuel Holders, Producers and Accessories 22.5 O

343 - Internal Combustion Engines 22.5 O

344 - Generators 22.5 0

345 - Accessory Electric Equipment 22.5

- 0 346 - Miscellaneous Power Plant Equipment 22.5 O

TRANSMISSION PLANT 350 - Easements 84**

65 0

352 - Structures and Improvements 24 43 (10) 353 - Station Equipment 24 34 (8) 354 - Towers and Fixtures - 345KV 24 30 (20) 354 - Towers and Fixtures - All other 24 40 (20) 355 - Poles and Fixtures - 345KV 24 30 (20) 355 - Poles and Fixtures - All Other 24 35 (20) 356 - Overhead cond. and Devices - 345KV

'24 30 0

356 - Overhead Cond. and Devices - All Other 24 45 0

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'S/85 l'ame B/2-14 ESTIMATED AVERACE USERIL LIVES FOR BOOK AND TAX PURPOSES AND NET SALEAGE MATES ELECTRIC PLANT (Continued)

Average Average Net

'l Life-Years Life-Years Salvage Account (Tax Purposes)

(Book Purposes)

(%)

i TRANSMISSION PLANT 357 - Undergr'ound conduit 24 41 0

t 358 -. Underground Conductors and Devices 24 36 2-

- 65 0

.i 359 - Roads and Trails 24 i

DISTRIBUTION PLANT 46**

55 0

360 - Easements

, 24 40 (10) a61 - Structures and Improvements 362 - Station Equipment 24

-30 8

364 - Poles, Towers and Fixtures 24 26 (22)-

365 - Overhead conductors and Devices 24 27 5

366 - Underground Conduit 24 59 (5) 367 - Underground Conductors and Devices 24 35 20 368 - Line Transformers 24 28 9

369 - Services 24 30 (13).

370 - Meters 24 30 -

0 m

371 - Installations on Customers' Premises 24 20 0

372 - Leased Property on Customers' Premises

.24; 12 (5) 373 - Street Lighting and Signal Equipment 24 15 O

CENERAL PLANT

- 390 - Structures and Improvements 45

.45 0

W1 - Office Furniture, Fixtures 8

'22' O

391 - Office Equipment 5

22 0

391 - EDP Equipment 5

392 - Transportation Equipment 393 - Stores - Equipment 24.

30 0

394 - Tools ' Shop and Garage Equipment.

24

. 35 -

0 395 - Laboratory Equipment.

' 24 -

35 0

396 - Power Operated Equipment

~*

397 - Communication Equipment 24 20 0 --

398 - Misc.allaneous Equipment 24 20-0-

Contact ' Finance and Accounting Group to determine life or salvage ' rate.

- Straight.Line Method c

s pi_

u.

Rev. 5 89 Pjage B/2-15 The various symbols have been chosen so that each is an initial letter w

of a key word associated with the most ccamon meaning of the'. symbol.

i t

-Thus i applies *to interest, n applies to number of years P applies to Presentworth,happliestofutureworth,andAappliestoannual payment or annuity.

4 Formulas. The Fundamental formulas that express the relationship bets'een

~

P. F. and A in terna of i and n are as follows:

Given P, to find F F=P (1+1)"

F = P (speaf,1%,n) 1 1-P = F (spywf,1%,n)

Given F, to find P P=F (1+i)"

~

i A = F (ussff,i%,n)

Given F, to find A A=F (1+i)" -1 i (1+1)

A = P (uscrf 1%,'n)

Given P, to find A A=P (1+i)" -1 I

or A=P

+1

~

(1+i)" -1 (1+i)

-1 F = A (uscaf.1%,n)

Given A, to find F F=A i

~

(1+1)n -1 P = A.(uspwf,1%,n)

Given A, to find P P=A 1 (1+1)"

or P=A i

+1 (1+1)" ~1

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Rev. 5 8/85-Dage P/2-16.

-

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A..............>.**

l 11.00% COMPOUND INTEREST. FACTORS

;; 2 2--

- ;;;;; - :.; ::az z a ::az;;;;.; ;;;;;;;;;;;;;;;;az ; :::.

SINGLE PAYMENT **

UNIFORM SERIES

: . :. :. ; ; :.. :.. : = :. :. :.. : :. :. :. :. :. :. :. :. ; :. :. ; :. ; :. ******************:. :, u :::. :. :. ; :. :. :. :. :.. :. :. :. = :. =

COMPOUND

PRESENT ** SINKING

CAPITAL

COMPOUND

PRESENT

AMOUNT

WORTH **

FUND

RECOVERY

AMOUNT *

-WORTH *

N*

FACTOR

FACTOR ** FACTOR.

FACTOR

FACTOR

FACTOR *

.,4S PWF L**

USSFF USCRF

USCAF USPWF

SPCAF

1*

1.11000

0.90090 **

1.00000 *. 1.11000 *" 1.00000

0.90090

2*

1.23210

0.81162 **

0.47393

0.58393 *- 2.11000

1.71252

3*

1.36763

0.73119 **

0.29921

0.40921

3.34210

2.44371

4*

1.51807

0.65873 ** 'O.21233

O.32233

4.70973

3.10245

5*

1.68506

0.59345 **

0.16057

0.27057

6.22780

3.69590

6*

1.87041

0.53464 **

0.12638

0.23638

7.91286

4.23054

7*

2.07616

0.48166 **

0.10222

0.21222

9.78327,*

- 4.71220

8*

2.30454

0.43393 **

0.08432

0.19432

11.85943 *- 5.14612

9*

2.55804

0.39092 **

0.07060

0.18060

14.16397

5.53705 *'

10*

2.83942

0.35218 **

0.05980

0.16980

16.72201'*

5.88923

i

11*

3.15176

0.31728 **

0.05112

0.16112

19.56143

6.20652 *

+

l

12*

3.49845

0.28584 **

0.04403

0.15403

22.71319 * -6.49236 * -

13*

3.88328

0.25751 *** 0.03815

0.14815

26.21164

6.74987 *

14*

4.31044

0.23199 **

0.03323

0.14323

30.09491

6.98187 *

15*

4.78459

0.20900 **

a.02907

0.13907

34.40535

7.19087 *

16*

5.31089

0.18829 **

0.02552 *.0.13552

39.18994

7.379161*

17*

5.89509

0.16963 **

0.02247

0.13247 *- 44.50084

7.54880 *

18*

6.54355

0.15282 **

0.01984

0.12984

50.39593 *- 7.70162 *

19*

7.26334

0.13768 **

0.01756.* 0.12756

56.93948 *: 7.83929 *

20*

8.06231

0.12403 **

0.01558

0.12558

64.20282.*:

7.96333 *

21*

8.94916

0.11174 **

0.01384

0.~12384 * - 72.26513 *-.8.07507 *-

22*

9.93357

0.10067 **

0.01231

0.12231

81.21429

8.17574 *

23*

11.02626

0.09069.**

0.01097

0.12097

91.14736 * ~8.26643 *

24*

12.23915

0.08171 **

0.00979 * -0.11979

102.17413

8.34814 *

~

25* 13.58546

0.07361 **

0.00874

O.11874

114.41328 * '8.42175 *

26* 15.07986

0.06631 **

0.00781

0.11781'* 127.99874

8.48806 *-

27w 16.73864

0.05974 **

0.00699

0.11699

143.07860 *; 8.54780

l

28* 18.57989

0.05382 **

0.00626

0.11626

159.81724 * ~ _8.60162

j t

29* 20.62368

0.04849 **

0.00561

0.11561

178,39714

8.65011

I

30* 22.89229

0.04368 **

0.00502

l

31* 25.41044

0.03935 **

0.00451_*~ 0.11502

199.02082

8.69379

0.11451'* 221'.91311 * - 8.73315

l 1

32* 28.20559

0.03545 **

0.00404 *.0.11404

247.32354 *~ 8.76860 *

{

33* 31.30820

0.03194 ** ~ 0.00363

O.11363

275.52913 *- 8.80054

1-

34* 34.75210

0.02878 **

C.00326

0.11326

306.83733

8.82932

1

35* 38.57483

0.02592 **.

0.00293

0.11293

341.58943

8.85524 *-

i

36*~ 42.81806

0.02335 **

0.00263

0.11263

380.16426 *

-8.87860 *-

37* 47.52805

0.02104 **

0.00236

0.11236

422.98233

8.89964

i

38* ~ 52.75613

0.01896 **

0.00213 * -0.11213

470.51038

8.91859

l

39* 58.35931

0.01708 **

0.00191

0.11191 *l523.26651'*.. 8.93567 *-

1 l-

40* 65.00083

0.01538 **'

O.00172,* 0.11172

581.82582 *. 8.95105 *

41* 72.15092

0.01386 **

0.00155

0.11155

646.82665 *' ~8.96491'*

t

42* 80.08752

0.01249'**-

~0.00139'*

0.11139

718.97757

8.97740 *

43* 88.89715

0.01125 SNr 0.00125 * '0.11115

799.06509 *.I 8.98865 *?

44* 98.67583

0.01013 **

0.00113'* -0.11113

887.96224 *: 8.99878 *.

45* 109.53017

0.00913 **

0.06101

0.11101

986.63807:*.

9.00791,*

f

46* 121.57849

0.00823 **

0.00091.* -0.11091 *1096.16825

9.01614'*

+

47* 134.95212

0.00741 **-.0.00082

0.11082 *1217.74674

9.02355 *'

c-

48* 149.79685

0.00668 **

0.00074

0.11074 *1352.69886

9.03022 *-

i i

. ~ _,,. _.. _

2.

2-

t Rev. 3-8/85 Page B/2-17 t

httachment 1 12.00% COMPOUND INTEREST FACTORS

. a ;. ;.: . :. :. ;. ;. = :. a a ;. = ;. :. a a ;. = :.

SINGLEPAYNENT UNIFORM SERIES-L 22: : - -

z a-a zaa a z zz a z z z ;--- -- azza z zaz z z az----------------

COMPOUND

PRESENT ** SINKING

CAPITAL

COMPOUND

PRESENT

i AMOUNT

WOR'IM **

FUND

RECOVERY

AMOUNT

WORTH * -

N*

FACTOR

FACTOR ** FACTOR

FACTOR * - FACTOR

FACTOR *.

l SPCAF

SPPWF **

USSFF USCRF

USCAF USPWF

a a aa zaazza;.;;;

aaaaaazzazazazzazzza :::az-azz- ; ;;;;:::az ::::az 1*

~ 1.12000

0.89286 **

1.00000

1.12000

1.00000 *7 0.89286

2*

1.25440

0.79719 **

0.47170

0.59170

2.12000

1.69005

0 3*

1.40493

0.71178 **

0.29635

0.41635 *-

3.37440 *

'2.40183

4*

1.57352

0.63552 **

0.20923

0.32923 *' 4.77933

3.03735 *~

5*.

1.76234

0.56743 **

0.15741

0.27741

6.35285

3.60478

6*

1.97382

0.50663 **

0.12323

0.24323

8.11519

4.11141

l 7*

2.21068

o.45235 **

0.09912

0.21912

10.08901

4.56376 * '

8*

2.47596

0.40388 **

0.08130

0.20130

12.29969

4.96764 *'

l 9*

2.77308

0.36061 **

0.06768

0.18768 *' 14.77566

5.32825 *

' l

10*

3.10585

0.32197 **

0.05698

0.17698

17.54873

5.65022 *

11*

3.47855

0.28748 **

0.04842

0.16842

20.65458

5.93770

l

12*

3.89598

0.25668 **

0.04144

0.16144 *' 24.13313

6.19A37 *

!~

13*

4.36349

0.22917 **' O.03568

0.15568

28.02911

6.42355 *

14*

4.88711

0.20462 **

0.03087

0.15087

32.39260 *

'6.62817~*

15*

5.47356

0.18270 **

0.02682

0.14682

37.27971 *

.6.81087 *

16*

6.13039

0.16312 **

0.02339

0.14339 * '42.75327 *-

6.97399 *

17*

6.86604

0.14564 **

0.02046 ** 0.14046

48.88367 *, 7.11963 *

18*

7.68996

0.13004 **

0.01794

0.13794

55.74971

7.24967

l

19*

8.61276

0.11611 **

0.01576

0.13576

63.43967_* 17.36578 *

20*

9.64629

0.10367 **

0.01388

0.13388

72.05243

7.46944 *

21* 10.80384

0.09256 **

0.01224

0.13224

81.69872 *. 7s56200 *

22*

12.10031

0.0826'. **

0.01081 *.0.13081

92.50256

7.64465

4

23*

13.55234

0.07379 **

0.00956

0.12956

104.60287

7.71843 *~

24*

15.17862

0.06588 **

0.00846 * ' O.12846 *-118.15521 * -7.78432 *

25*

17.00006

0.05882 **

0.00750

0.12750

133.33333

7.'84314 *

26*

19.04006

0.05252 **

0.00665

0.12665

150.33389 *

- 7.89566 *

27* 21.32487

0.04689 **

0.00590

0.12590

169.37396

7.94255 *

28* 23.85386

0.04187 **

0.00524

0.12524

190.69883

7.98442 *-

29* 26.74992

0.03738 **

0.00466

0.12466.* 214.58268

8.02181 *

'20*

29.95991

0.03338 **

0.00414

0.12414

241.33260

8.05519 *

31*

33.55510

0.02980 **

0.00369

0.12369

271.29251.*

8.08499 *

32*

37.58171

0.02661 **

0.00328 *.0.12328

304.84761 *

- 8.11160 *

33* 42.09151

0. 2376 **

0.00292

0.12292

342.42931:*

8.13535 *

34* 47.14249

0.02121 **

0.00260 * -0.12260

384.52083

8.15657 *

35* 52.79959

0.01894 **

0.00232

0.12232

431.66332 *. 8.17551 *

36* 59.13554

0.01691 **

0.00206

0.12206

484.46291 *

-8.19242 *

37* 66.23180

0.01510 **

0.00184 *.0.12184

543.59845 *

-8.20731 *

38*

74.17962

0.013oE **- 0.00?64

0.?2164

609.83025

8.22099 *

39*

83.08117

0.01204 **

0.00146 * '0.12146

684.00987.*

8.23303 *

40* 93.05091

0.01075 **

0.00130

0.12130

767.09105 * - 8.24378 *

41* 104.21702

0.00960 **

0.00116

0.12116

860.14196'*-

8.25337 *

42* 116.72306

0.00857 **- 0.00104

0.12104

964.35898 *-

8.26194'*

43* 130.72983

0.00765 **

0.00092'* 0.12092 *1081.08204 *

'8.26959

O'

44* 146.41740

0.00683 **

0.00083

0.12083 *1211.81186'*

8.27642 *

45* 163.98749

0.00610 **

0.00074

0.12074 *1358.22927 * ' 8.28252 *

46* 183 66598

0.00544 **

0.00066

0.12066.*1522.21675 *.

8.28796 *-

s.

47* 205.70590

0.00486 **

0.00059 *. 0.12059 *1705.88274

8.29282 *

48*'230.39060

0.00434 **

0.00052

0.12052 *1911.58864 * '8.29716

7

...,,.mN.,,..p

--,w, a

w

--,,--=,e e

l 1

-Rev. 5 l

A/85-1 P a g e - B / 2 -18 '

~

j.

. : ;;. :. :. :. :. ; :. :. :. :. :. :. : :. ases we++wesw; ; ; ;. :... :. :. ;. :.*

13.00% COMPOUND INTEREST FACTORS

~

. :. :. :. :. :. :. :. :. ;m******

i SINGLE PAYMENT **

UNIFORM l

. SERIES

COMPOUND

PRESENT ** SINKING

CAPITAL * ' COMPOUND *-

PRESENT *

- AMOUNT

WORTH- **

FUND

RECOVERY

AMOUNT.

WORTH *

N*

FACTOR

FACTOR **' FACTOR

FAC'1VR.*

FACTOR

FACTOR

I SPCAF

SPPWF **. USSFF

-USCRF

USCAF USPWF *

'1*

1.13000

0.88496 **

1.00000 *.1.13000

1.00000 *- 0.88496 *

^

2*

1.27690

0.78315 **

0.46944

C.59948

2.13000

1.66810

3*

1.44290

0.69305 **- 0.29352

0.42352 *~ 3.40690 *~ 2.36115

4*

1.63047

0.61332 **

0.20619

0.33619

4.84980 *- 2.97447

5*

1.84244

0.54276 **' O.15431

0.28431 * '6.48027 * -3.51723

6*

2.08195

0.48032 **

0.12015

0.25015

8.32271

3.99755

i 7*

2.35261

0.42506 **

0.09611

0.22611

10.40466

4.42261

8*

~ 2.65844

0.37616 **

-0.07839

0.20839

12.75726

4.79877

9*

3.00404

0.33288 **

0.06487 *. 0.19487

15.41571 * - 5.13166 *

10*

3.39457

0.29459 **

0.05429

0.18429

18.41975

5.42624 *

11*

3.83586

0.26070 **

0.04584

0.17584

21.81431

5.68694

si

12*

4.33452

0.23071 **

0.03899

0.16899

25.65017

5.91765 *

'l

13*

4.89801

0.20416 *** 0.03335

0.16335 */ 29.98470

B.12181 *.

14*

5.53475

0.18068 **

0.02867

0.15867

34.88271

6.30249 *

15*

6.25427

0.15989 **

0.02474

0.15474 *.40.41746 *' L6.46238

I

16*

7.06732

0.14150 **

0.02143

0.15143

46.67173 *'

6.60388

i

17*

7.98608

0.12522 **

0.01861

0.14861 * -53.73905 * '6.72909 *

18*

9.02427

0.11081 **

0.01620

0.14620

61.72513 *-

6.83991 *

-j

19* 10.19742

0.09806 **

0.01413

0.14413

70.74939 *. 6.93797

J

20*

11.52308

0.08678 **

0.01235

0.14235

80.94681 * ' 7.02475 *-

l

21* 13.02108 *'0.07680 **

0.01081 *. 0.14081

92.46989 * :7.10155 *-

-l

22* 14.71383

0.06796 **

0.00948

0.13948

105.49098

7.16951

I

23* 16.62662

0.06014 **

0.00832

0.13832 *-120.20480

7.22966 *

24*

18.78808 *-0.05323 **

0.00731'* 0.13731.* 136.83143

7.28288 *

25* 21.23053

0.04710 **

0.00643

0.13643 *.155.61951 *.7.32999 *

26* 23.99050

0.04168 **

0.00565 * ^0.13565 *'176.85004 *

'7.37167 *

27* 27.10927

0.03689 **

0.00498

0.13498

200.84054 *

'7.40856 *

28* 30.63347

0.03264 **- 0.00439

0.13439 *-227.94981

7.44120 *

29* 34.61582

0.02889 **

0.00387

0.133871* 258.58328

7.47009 *

30* 39.11588

0.02557 **

0.00341 *. 0.13341

293.19910

7.49565 *~

l

31* 44.20094

0.02262 **

0.00301

0.13301'* 332.31498.*

7."$1828 * '

32* 49.94706

0.02002 **

0.00266 * '0.13266 *;376.515921*

-7.53830 *:

3

33* 56.44018

0.01772 **

0.00234 *. 0.13234

426.46298

7.55602 *

34* 63.77740

0.01568 **

0.002071* '0.13207.* 482.90316

7.57170 *

35* 72.06846

0.01388 **

0.00183 *70.13183

546.68056 * '7.58557 *_

36* 81.43736 *.0.01228 **

0.00162 *

37* 92.02422

0.01087 **- 0.00143 *~ 0.13162 *:618.74903

7f.59785 *-

0.13143

700.18639

7.60872'*

38* 103.98736

0.00962 **

0.00126

0.13126

792.21060.*

'7.61834 *

39* 117.30572

0.00851 **

0.00112 *' O.'13112'* 896.19797

7.62685 *'

40* 132.78146

0.00753 **

0.00099

0.13099 *1013.70369 *= 17.63438 *

41* 150.04305

0.00666 **

0.00087

0.13087 *1146.48514

7.641041*

42* 169.54864

0.00590 **

0.00077

0.13077. *1296.52819 *.7.64694 *

43* 191.58996

3.00522 **

0.00068

0.13068 *1466.07683 *:

7.65216 *-

J

44* 216.49665

0.00462 **

0.00060 *' O 13060 *1657.66679

7.65678.*

(

45* 244.64121

0.00409.**

0.0.0053 * '0.13053 *1874.16344'*; -7.66087

i

46* 276.44456

0.00362 **

0.00047

0.13047 *2118.80465

7.66448'*

'~

47* 312.3,8235

0.00320 **

0.00042

0.13042 *2395.24921 *

' 7.66768l*

j

48* 352.99205

0.00283 **

0.00037 *: 0.13037 *?*07.63156 * 'f7.67052-*

d

Rev. 5 8/85 Page B/2-19 L

azzaa:.zazzazaazaaaaaaaaa:az;az z aaa;;aaz;;; a:.

a z a z a z z a z ; ; ;;;. ;;. :a ;. ze*****

14.00% CO.MPOUND INTEREST FACTORS

..vww**

a z z a z;;;; ::::::: ::a z z,;;; a a a a :. a z ;*****;;;;.;; :.:.;;:.a a a a z a;;;;;;;;.a :.

SINGLE PAYMENT **

UNIFORM SERIES z a a z z a z z a z z a z z a a a a :a z a z a z z ;.a z z a a :a z z a a z z a a a a :.:a z a z a :a a :a. :. ::::. :.******

COMPOUND

PRESENT ** SINKING

CAPITAL

COMPOUND

PRESENT *'

AMOUNT

WORTH **

FUND

RECOVERY

AMOUNT

WCRTH *

N*

FACTOR

FACTOR ** FACTOR '* FAT'OR

FACTOR

FACTOR

SPCAF *.SPPWF **

USSFF U1 RF

USCAF USPWF *-

az:.zaza;;;azaaaaa:.a:.;;;;; zaaaaaaaa:a aazzazz-

.: a zz ;;; szaaaaa;;;;.ia ;;.:a:.

1*

1.14000

0.87719 **

1.00000

1.14000

1.00000

0.87719

2*

1.29960

0.76947 **

0.46729

0.60729

2.14000

1.64666

3*

1.48154

0.67497 **

0.29073

0.43073

3.43960

2.32163

4*

l'.68896

0.59208 **

0.20320

0.34320

4.92114

2.91371 *-

5*

1.92541

0.51937 **

0.15128

0.29128

6.61010

3.43308

6*

2.19497

0.45559 **

0.11716

0.25716

8.53552

3.88867

7*

2.50227

0.39964 **

0.09319

0.23319

10.73049

4.2S831

8*

2.85259

0.35056 **

0.Q7557

0.21557

13.23276

4.63886

9*

3.25195

0.30751 **

0.06217

0.20217

16.08535

4.94637 *

10*

3.70722

0.26974 **

0.05171

0.19171

19.33729

5.21612 *

11*

4.22623

0.23662 **

0.04339

0.18339

23.04451

5.45273 *

12*

4.81790

0.20756 **

0.03667

0.17667

27.27075

5.65029 *

13*

5.49241

0.18207 **' O.03116

0.17116

32.08865

5.84236 *

14*

6.26135

0.15971 **

0.02661

0.16661

37.58106

6.00207 *

15*

7.13794

0.14010 **

0.02281

0.16281

43.84241

6.14217 *

~

16*

8.13725

0.12289 **

0.01962 *' O.15962

50.98034

6.26506

O

17*

9.27646

0.10780 **

0.01692

0.15692

59.11759

6.37286 *

18*

10.57517

0.09456 **

0.01462

0.15462 *. 68.39405

6.46742 *

19* 12.05569

0.08295 **

0.01266

O'.15266

78.96922

6.55037 *'

20* 13.74348

0.07276 **

0.01099

0.15099

91.02490 *'

6.62313 *

21* 15.66757

0.06383 **

0.00954

0.14954

104.76839

6.68696 *-

22* 17.86103

0.05599 **

0.00830 *' O.14830

120.43596

6.74295 *

23* 20.36158

0.04911 **

0.00723

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138.29699

6.79206 *

24* 23.21220

0.04308 **

0.00630

0.14630

158.65857

6.83514 *

25* 26.46190

0.03779 **

0.00550

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181.87077

6.87293

l

26* 30.16657

0.03315 **

0.00480

0.14480

208.33267

6.90608 *'

27* 34.38989

O.02908 **

0.00419

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238.49924

6.93516 *~

[

28* 39.20447

0.02551 **

0.00366

0.14366

272.88913

6.96066

l

29* 44.69310

0.02237 **

0.00320 *- 0.14320

312.09360 *:

6.93304

i

30* 50.95013

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0.00280

0.14280

356.78669 *

'7.00267 *

31* 58.08315

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0.00245

0.14245.* 407.73682

7.01988 *

32* 66.21479

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0.00215

0.14215

465.81997

7.03498 *

33* 75.48485

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0.00188

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532.03476

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M

34* 86.05273

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0.00165

0.14165

607.51961 *~ 7.05985 *

35* 98.10011

0.01019 ** - 0.00144

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693.57234-*

7.07005 *

36* 111.83413

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0.00126

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791.67245

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37* 127.49090

0.00784 **- 0.00111

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903.50658

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l

38* 145.33963

0.00688 **

0.00097

0.14097 *1030.99748

7.09371 *

39* 165.68717

0.00604 **

0.00085

0.14085 *1176.33711

7.09975 *

40* 188.88337

0.00529 **

0.00075

0.14075 *1342.02428

7.10504 *

41*'215.32704

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0.00065

0.14065 *1530.90765

7.10969 *

42* 245.47282

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7.11376 *

43* 279.83901

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7.11733

O

44* 319.01646

0.00313 **

0.00044

0.14044 *2271.54651 *.

7.12047 *

45* 363.67876

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0.14039 *2590.56297'*

7.12322

e

46* 414.59378

0.00241 **

0.00034

0.14034 *2954.24173

7.12563 *

47* 472.63690 *-0.00212 **

0.00030 * '0.14030 *3368.83551 * '7.12775

e I

48* 538.80605

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0.00026

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7.12960

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Rav. 5 8/85 Page B/2-20

]

}

- - - - -. :. :. :. ;. :. :. ;. :. :. :. :. :. :. :. :. :. :. :. :. ;. :. :. : ;, :. ;. :. :, ; :. :. ;. :. :. :. ;. :. :. c. ;. :. :. :. :. :. :. :. :. a ;. :, ;. :. :. :. :. :. :. a**

15.00% COMPOUND INTEREST FACTORS

- - - e.a ;;;;; a z z a a a a a a z a ;;, a z a z z a :. ;. a a a a ;a z a a a a :. ; ;. :. z a z z a :. z a z a z z a a a z z a a a ;

SINGLE PAYMENT **.

UNIFORM SERIES

- - - - a z z a ;. a a z z :. z a z :. ;;. z z :. ; ; ;; ;;;;. a z a z z a a ; ;;. a a a a :. :. a a a a a ;. :: :: : :. :. a. ; ; ;. a :.

COMPOUND

PRESENT ** SINKING * -CAPITAL *- COMPOUND

PRESENT

4 AMOUNT *- WORTH **

FUND

RECOVERY *-

AMOUNT

WORTH *

N*

FACTOR

FACTOR ** FACTOR

FACTOR

FACTOR

FACTOR

SPCAF

SPPWF **

USSFF USCRF

USCAF.

USPWF *

a z a a a a ;;. a z z a ;;. ;;. z a z a z

.

. z a a a a a a a a a z z a z z a z a z a a ;. ;;;;;. ;

. a a

. a a a a a a a a a a: .a a **

1*

1.15000

0.86957 **

1.00000

1.15000

1.00000

0.86957

2*

1.32250

0.75614 **

0.46512

0.61512

2.15000

1.62571

3*

1.52087

0.65752 **

0.28798

0.43798

3.47250

2.28323

4*

1.74901

0.57175 **

0.20027

0.35027

4.99337

2.85498

5*

2.01136

0.49718 **

0.14832

0.29832

6.74238'*

3.35216

6*

2.31300

0.43233 **

0.11424

0.26424

8.75374

3.78448

1 J

7*

2.66002

0.37594 **

0.09036

0.24036

11.06680

4.16042

8*

3.05902

0.32690 **

0.07285

0.22285

13.72682

4.48732

9*

3.51788

0.28426 **

0.05957

0.20957

16.78584

4.77158 *

10*

4.04556

0.24718 **

0.04925

3.19925

20.30372

5.01877 *

11*

4.65239

0.21494 **

0.04107

0.19107

24.:34927

5.23371 *

12*

5.35025

0.18691 **

0.03448

0.18448

29.00166

5.420~62 *

13*

6.15279

0.16253 **

0.02911

0.17911

34.35191

5.58315

i

~

14*

7.07570

0.14133 **

0.02469

0.17469

40.50470

5.72448 *

15*

8.13706

0.12289 **

0.02102

0.17102

47.58040

5.84737 *

16*

9.35762

0.10686 **

0.01795 ** 0.16795

55.71746

5.95424 *

\\

17* 10.76126

0.09293 **

0.01537

0.16537

65.07508 *.

6.04716 *

18* 12.37545

0.08081 **

0.01319

0.16319

75.83634 *- 6.12797

6.19823 *

19* 14.23177

0.07027 **

0.01134

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88.21179 *_ '6.25933

s,

20*

16.36653

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21*

18.82151

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118.81008 *- 6.31246 *

22* 21.64474

0.04620 **

0.00727

0.157?7

137.63159

6.35866 *

23* 24.89145

0.04017 **

0.00628

0.15628

159.27633 *- 6.39884 *-

24* 28.62516

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0.00543

0.15543

184.16778

6.43377 *

25* 32.91894

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b.00470

0.15470

212.79294

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26* 37.85678

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327.10394

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l

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0.00265

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30* 66.21173

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0.00230

0.15230

434.74494

6.56598 *

31*

76.14349

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0.00200

0.15200

500.95667 *'

6.57911=*

32* 87.56501

0.01142 **

0.00173

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577.10016 *

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33* 100,69976

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34* 115.80472

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0.00131

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6.60910 *'

35* 133.17543

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0.00113 * -0.15113

881.16965

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36* 153.15174

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0.00099

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37* 176.12449

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0.00086

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6

38* 202.54316

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6.63375.*

6.63805 *-

39* 232.32463

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0.00065

0.13065 *1546.16448

_ 6.64178 *

40* 267.86332

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0.00056

0.15056 *1779.08911 *

41* 308.04282

0.00325 ** -0.00049 *: 0.15049 *2046.95243 * - 6.64503 *

42* 354.24923

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0.15042 *2354.99525

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43* 407.38661

0.00 0.00037 *. 0.15037 *2709.24448 * '.6.65030 *

44* 468.49459

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0.00032 *. 0.15032 *3116.63109 * - 6.65244 *

'* 45* 538.76877

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0.000'28 *- 0.15028 *3585.12568 * ' 6.65429 *

46* 619.58407

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0.00024

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47* 712.52166

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48* 819.39990

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8/85.

Page B/2-21 O

2

.16.00% COMPOUND INTEREST FACTORS

_ _ _ _ ; _ _ ;;;;;;; ;;; _ ; ;; ; _ ;; _ ; _ ; ; _ _ ; _ ;;;;; ;; _ ;;;; _ ;;;;;;; _ _ ;;; _ ; ;; ;;;;;; c.*****

SINGLE PAYMENT **

UNIFORM SERIES t

COMPOUND

PRESENT ** SINKING

CAPITAL

COMPOUND

PRESENT

l AMOUNT

WORTH **

FUND

RECOVERY

AMOUK! *-

WORTH '*

~

N*

FACTOR-

FACTOR ** FACTOR

FACTOR *

{ ACTOR:

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i'

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SPCAF -* SPPWF -**

USSFF

. USCRF

_ <USCAF.

1*

1.16000

0.86207 **

1.00000

1.16000

1.00000 *.0.86207

2*

1.34560

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1.56090

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0.28526

0.44526

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1.81064

0.55229 **

0.19738

0.35738

5.06650 *

'2.79818-*

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5*

2.10034

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0.14541

0.30541

6.87714

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2.43640

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3.68474

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2.82622

0.35383 ** '0.0'8761

0.24761 *- 11.41387 *.

4.03857

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3.27841

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0.07022

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0.26295 **

0.05708

0.21708

17.51851 *.

4.60654 *~

10*

4.41143

0.22668 **

0.04690

0.20690

21.32147

4.83323 *

11*

5.11726

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0.03886 * '0.19886

25.73290

5.02864 *

12*

5.93603

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0.03241

0.19241

30.85016

5.19711 *'

i

13*

6.88579

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0.02718

0.18718 *- 36.78619

5.34233 *-

l

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7.98752

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0.02290

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O.01936

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31.65949 * :5.57546

l

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17* 12.46768

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18*

14.46251

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0.01188 * 'O.17188

84.14069

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19*

16.77651

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0.01014

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20*

19.46075

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21* 22.57447

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0.00742.* '0.16742.* 134.84046 *- 5.97314

i

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30.37621

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616.16128L* 16.18724 *,

32* 115.51951

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715.74706 *- 6.19590 *-

-33* 134.00263

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0.00120 *'~0.16120

831.26658

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~

34* 155.44305

0.00643 **

0.00104 * -0.16104

965.26921 *. 6.20979 *-

35* 180.31393

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0.00077 *- 0.16077 *1301.02619 *

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40* 378.72082

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l

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42* 509.60671

0.00196 ** -0.00031 * '0.16031.*3178.79247

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43* 591.14377

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2

44* 685.72676

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0.00023 *.0.16023 *4279.54295 *

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0.16020 *4965.26972

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46* 922.71389

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0.00017 * '0.16017 *S760.71274'*-

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47*1070.34809.* 0.00093 **

0.00015.* 0.16015 *6683.42663 *.

6.24416 *

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UNIFORM =

SERIES l

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PRESENT ** SINKING

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WORTH **

FUND

RECOVERY

AMOUNT

WORTH '*

N*

FACTOR

FACTOR '** FACTOR

FACTOR

FACTOR *- FACTOR

SPCAF *' SPPWF. **

USSFF

.USCRF'

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e t. = = u u = a :. :. ;;. = = :. ;. :. = = = : a u u******** ;. :. :. :. :. :. ; ;. a :. ;. :. :. :. :. :. u ;. :. ; :. :. :. ;. :. ;. :.

1*

1.17000

0.85470 **

1.00000

1.17000

1.00000 *' O.85470

2*

1.36890

0.73051 **

0.46083

0.63083

2.17000

1.58521~*

3*

1.60161

0.62437 **

0.28257 * -0.45257

3.53890

2.20959

4*

1.87389

0.53365 **

0.19453

0.36453

5.14051

2.74324

7.01440

3.19935

5*

2.19245

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0.14256 *: 0.31256 *.

9.20685

3.58919 *

. 6*

2.56516

0.38984 **

0.10861

0.27861

7*

3.00124

0.33320 **

0.08495

0.25495

11.77201

3.92238 *-

8*

3.51145

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0.06769

0.23769

14.77325

4.20716

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4.10840

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18.28471

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10*

4.80683

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0.04466

0.21466 *. 22.39311

4.65860.*

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11*

5.62399

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0.03676 * '0.20676

27.19993

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12*

6.58007

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13*

7.69868

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0.19538 * ' 39.40399

5.11828

i

14*

9.00745

0.11102 **

0.02123

0.19123 *' 47.10266

5.22930

i

15* 10.53872

0.09489 **

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56.11011

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16*

12.33030

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0.18500 * -46.64483

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17*

14.42645

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0.01266

0.18266'* 78.97913

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18*

16.87895

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0.01071

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19.74837

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20* 23.10559

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130.03289 * '5.62777 *

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29* 94.92699

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0.17032 *3134.51935

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0.00100 **

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~

O NORTHEAST UTILITIES CORPORATE MANAGEMENT PR0r: RAM FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE PART B PROCEDURE #3~

s' AUDITS AND APPRAISALS OF THE. STATIONS' HEALTH PHYSICS PROGRAMS O

Reviews Completed and Coments Resolved Manager, Radiological Assessment Branch, NUSCO Procedure Approved

. b $JN :

Senior Vice President, Nddlear Eng. & Opers.,

NUSCO, NNEC0, CYAPC0 O

Date

-i V

-. ~.., _....

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r.

Rev. 8 Date 1/86 Page B/3-1 1.0 PURPO:E.

1.1 ro perform routine and documented audits and appraisals of the health physics programs et Millstone and Haddam Neck, and the radiological protection programs of the Middletown Station.and the NUSCO Personnel Dosimetry Laberatory. The purpose of the audits is to:

1.2 Check compliance with the applicable requirements of 10CFR, Technical Specifications, the Corporate ALARA Program, station procedures, Corporate Standardized Health Physics Procedures, departmental instructions and By-Product Material Licenses.

1.3 Provide sta, tion and.NUSCO Nuclear Engineering and Operations Senior Management with an effective means to monitor the overall quality of the station health physics programs and initiate corrective actions as necessary.

2.0 APPLICABILITY 2.1 To all aspects and requirements of the station health physics program.

J 2.2 To all personnel involved with the station health physics programs.

3.0 REFERENCES

Hnne.

4.0 DEFINITIONS 4.1 Audit An independent and documented activity performed in accordance with written procedures and checklists to determine, by examination of objective evidence, that applicable elements of the Health Physics Program have been developed, documented, and effectively implemented in accordance with regulatory requirements and applicable company policies and procedures.

4.2 Appraisal A documenteil activity performeil in accordance wIth written.

~

procedures and checklists to evaluate th'3 relative worth and status of various elements of the Health Physics Program and to provide recomendations for programatic improvement.

4.3~ Corrective Action Action taken by the audited or appraised organization to modify or revise health physics program controls as necessary to preclude the-recurrence of a finding.

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Rev. :t t

Dale I/36 Page 11/3 2 4.4 Healtn Physics Programs All.E:tivities within the purview of,the station health physics..

department including, but not limited to, Radiation Worker Training programs, health physics personnel training, radioactive waste management and the station ALARA program.

j 5.0 RESPONSIBILITIES e

5.1 Station Superintendent 5.1.1 Assuring' that health physics personnel and all plant records, reports and documentation records-containing health physics related information are made available to the' auditors in a.

reasonable' time frame.

5.1.2 Assuring that audit findings are resolved within the required; time frame.

5.2 Supervisor, Radiological Pretection Section (NUSCO Radiological Assessment Branch) o 5.2.1 Assuring that audits and appraisals are performed at the i

required frequency, that the appropriate audit classification, documentation and corrective actions are followed,.and that auditors clear items in the reports,'as soon as possible, with-i the statio.n to avoid. extended audit-items.

5.2.2 Maintaining complete file of. audit reports.

5.2.3 Preparing the Reports in Item 8.6.

5.2.4 Training auditors to follow this procedure.

5.2.5 Conducting prompt audit debriefing sessions to facilitate the timely correction of findings.

5.3 Manager, Radiological Assessment Branch,'NUSCO

$ 3.L Resolving all audit items not resoluable by due process.

i 5.3.Z ~

Notifying as soon as possible senior NU management'as necessary offitems of significance.

6.0 PREREQUISITES

'i l

6.1 Auditors should notify health physics (HP) supervision of the i

expected date(s) of the audit prior to arrival on site. The~date l

and time of exit' interview will be scheduled.

6.2 Auditors should check the current file of open audit' items' prior to thecaudit to vetermine if there are any that should.be checked for-completion.

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Page R/3-3 4$

6.3 - Periodic unannounced au'dits will be conducted in which case item 6.11 does.not apply.

L 7.0 PRECAUTIONS 7.1 -An exit interview (in person'or by phone depending on. availability of statior supervision)- should be conducted before finalization of ~

4 any audit findings.

7.2 Reconenendations should be written only if there is a' reasonable agreement _t_ hat it is necessary to maintain compliance or quality assurance or that it would lead to an improvement in the health

{

-physics program.

l' 7.3 The auditors will exercise stop work authority through the on-job HP supervision or job supervision, as necessary, to ensure compliance-with regulations.

If the items are serious, including but not-l limited to stopwork action, the. auditor will inmediately' conduct a person to person meeting with the Station Superintendent'and the Health Physics Supervisor (or their designated alternates if they i

are away from the st1 tion) to attempt to resolve the difficulties.

If items are not inmediately resolved at this level, the auditor wi11 notify the NUSC0/ Radiological Assessment Branch (RAB)

Management. The Manager RAB-shall notify appropriate senior NUSCO management including the Vice President of Nuclear Operations.

7.4 A walk-through type audit to check for area postings,' rad' material control, RWP compliance, etc., shall be performed-as a part of each-audit unless a'reas are inaccessible.

~

4 8.0 INSTRUCTIONS 8.1 Audit Schedule i-8.1.1 An audit of each nuclear station should-be performed at:least.

monthly. During outages, the audit frequency should.be-j increated to once a week. This frequency will remain flexible j

and may increase or' decrease during an outage _ depending upon.

the amount and type of activity occurring at the nuclear; station. and the number of' audit items being documented.1.

Documentation in the form of a memo from the Supervisor'of the Radiological Protec. tion Section to the Manager.of the

-Radiological Assessment Branch is required stating the reasons

{

for changing the outage audit frequency from once:a week.-

8.1.2 Audits of the Middletown Station Environmental,TLD Calibration Facility and the NUSCO Dosimetry; Laboratory Radiation Protection Programs should be performed at least annually.

8.1.3 Prior to, or initially during major outages atinuclear= units, a thorough audit / appraisal of Health Physics preparedness will-also be performed.

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Rev. 3 Dale 1/lM Page 8/3-4 8.1.4 Table 1 lists the categories which shall be audited. Each category listed shall be audited.at least once each calendar year at each site. Table 1 gives guidance as to which-items should be concentrated on during outage periods and during non-outage periods. Note that certain categories.(3, 4, 7, 9, 10, 11,15-17,20,22) on Table 1 are not applicable to by-product licenses and do not apply to the Middletown Station or the NUSCO Personnel Dosimetry Laboratory.

8.2-Audit Procedure 8.2.1 The auditor should try to establish mutually agreeable. dates

~

and times for the audit and exit interviews with the Health Physics Supervisor and a Superintendent or their designees.

For unannounced audits this is not necessary.

3.2.?

The auditor should determine which categories from Table 1 will be audited. The categories to be audited.do not have to be

~

specified to the plant staff prior to the audit. A walk-through type audit shall be performed as a part of each audit.

8.2.3 The auditor should check the current file of open audit items to determine if any are past the requi_ red corrective action date.

If they are, they should be checked during the audit.

8.2.4 The auditor silould-announce his (h'er) presence to hea,lth phisics supervision and/or station management upon arrival.

If unavailable the auditor will inform the station management administration secretary. The approximate time of the exit interview should,be confirmed.

8.2.5 Upon completion of the audit, the auditor should complete steps 8.2.6 and 8.2.7 below but not necessarily in that order listed. However, they should be completed before going to step 8.2.8.

8.2.6 The auditor should conduct an exit interview with the Health Physics Supervisor (and Station Services Superintendent when items of Noncompliance I classification have been identified) or their designee. When non-H.P. findings are identified, the auditor shall have the Station Services Superintendent identify the Responsible Supervisor whose name will be entered on the Audit Finding Form.- If unavailable on the day of the _ audit, the exit interview can be conducted by phone or by return visit-within a reasonable time frame except with a significant finding for which the auditor must talk to plant management-

-prior to leaving'the site. The exit interview shall be conducted prior to a finalization of the audit findings. Any differences on audit _ findings should be resolved by the Station Services Superintendent and the Manager RAB.

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Rev.-8 I

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'Page-B/3 C2 3.7./

The amlitor shou'ld complete any Audit Finding Forms in the-inanner prescribed in Section 8.4.

t I-8.2.8 Copies of Audit Fin' ding Forms should be given to or left for the Health Physics Supervisor.

In the case of a non-HP finding-an additional copy should be left for the Station-Services Superintendent.

8.3 The Audit Report 8.3.1 Within a 2-3 day time frame following the audit exit interview,-

the audit report should be issued to the audited organization:

by the Training ~and Audits Unit, RA8.-

a 8.3.2 The Auditor prepares the. Audit Report. The audit report may be typed or handwritten in the following format:

1.0 Introduction 2.0 Audit Management Summary 3.0 -Audit Details 4.0 Status of Previous Findings 5.0 Attachments

- 8.3.4 The Introduction, Section.(1.0) of the Audit Report shall i

identify,the auditee (what station, department, laboratory,

, O-etc.), the audit categories,- the dates of the audit,=the-personnel contacted during the audit, the personnel present at' 4

the audit exit interview, and auditor man-hours expended during.

the performance of the audit.

8.3.5 The Audit Manaqement Sumary, Section (2.'0) of tne Audit-Report. -

shall provide a short listing.of any audit. findings and.their.

l l

respective level of severity.. The Sumary shall also be 'used i

to identify problems of a' recurring nature and to-include the l

auditor's impression relating to the overall effectiveness of' the portion of the Health Physics Program observed dur_ing.the l

audit.

i

]

8.3.6 The Audit Details, Section (3.0).of the Audit Report-shall l

include a detailed listing of the audit criteria and the..

d auditor's observations and findings,'if any, following each.

criterion.

4 8.3.7 The Status of Previous Findings, Section (4.0) of the Audit Report shalT include a compilation of the findings closed during the performance of the audit, -if any, and a listing of-all remaining open findings. Findings which are approaching or-

~

have passed their corrective action due dates, at the time of the report, shall be so-noted.

8.3.8' The Attachments, Section (5'.0)of the Audit Report shall.

contaiu a copy of each Audit Finding Form issued'during the audit.

O This sectior:will also be available for'the documentation of.

any auditor notes, check lists,. data-sheets, photocopies off

!~

plant documents, etc., that were collected.during.the audit.-

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4 Rev. 8-Date 1/86 Page B/3-6 V

3.3.9 Sign and date the Audit Report.

If more than one auditor'was involved, both should sign.

8.3.10 Distribute the Audit eport in accordance with the following:

3.3.10.1 For Nuclear Station Audits Addressee:

. Station Superintendent Distribution: Responsible Supervhor(s)

Station Services Superintendent Rad. Services Supervisor - Millstone H.P. Supervisor - Millstone and Conn. Yankee V.P. - Nuclear Operations V.P. - Nuclear and Environmental Engineering Director - Nuclear. Engineering Manager - RAB Supervisor - Rad. Prot. Sect;, RAB RAB File 8.3.10.2 For NU Dosimetry Laboratory Audits Addressee:

Dosimetry Laboratory Su;;ervisor Distribution: Supervisor - H.P.-Programs Sect., RAB H.P. Supervisor - Millstone and Conn. Yankee V.P. - Nucl'ar Operations e

V.P. - Nuclear and Environmental Engineering Director - Nuclear Engineer.ing g

Manager - RAB Supervisor - Rad. Prot.' Sect., RAB RAB File 8.3.10.3 For Production Operation Services Laboratory Audits Addressee:

Supervisor - POSL Distribution: Manager - Production and Operations Services Supervisor -Radiological Engineering Section, RAB V.P. - Nuclear and Environmental Engineering Director'- Nuclear Engineering Manager - RAB Supervisor - Rad. Prot. Section, RAB RAB File 11. 4 Completion of the Audit Finding Form - Part 1 o

8.4.1 Enter the finding. number as follows: Calendar.date - Sequence' number. The sequence number would start at 1 for each' audit; e.g., 2 audit items identified on a March 15, 1982 audit would be numbered 3-15-82-1, 3-15-82-2.

3.4.?

Circle the appropriate unitis).

8.4.3 Describe the item in sufficient detail.

If a number of.

separate but very similar items are identified, they may be grouped as one audit item if they are addressed to the same individual.

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U.4.4 Determine an'd check the classification of the' Item (s) as follows-(1) Non-Compliance'I - Violation'of Federal' Regulations, i

~ Technical Specifications or By-Product Material", license, cor. station and corporate procedures necessary to show compliance with the above..

.(2) Non Compliance II - Violation of those-station procedures,

~

station orders, Corporate ALARA program, or Corporate.

g Standardized Health Physics' Procedures that go beyond

~

ensuring compliance with regulatory criteria.

(3) Deficiency -- No apparent violation, but a lack of approve <f written procedures,. written documentation, etc., to show compliance'with 10CFR, Technical Specifications, Station Procedure or~ Corporate ALARA program.-

I (4) Reconnendation None of the above. A suggested

- i progrannatic improvement in the health physics program to-

= i more completely assure compliance or improve quality.-

Explain the reason for the reconnendation,- based on-facts and-not just a personal preference.

NOTE:

For non-compliances, enter the specific-regulation, technical specification or procedure-j'O which was violated. Group items together as examples 1of the same Noncompliance and'not separately.

j 8.4.5 In the event of significant findings that)are consider.ed to bel, 3

serious by the auditors or RAB supervision, the' Station j

Superintendent and Manager RA8 will be informed innediately.

~

Depending on the seriousness and at the discretion of the Manager, RAB, senior NUSCO Management ~(including V.F. Nuclear Operations) will be. informed. Section 7.3 will be adhered to l

for all stop work situations.

5 l

Check the appropriate priority and specify a-suggested due-8.4.6 date. For reconnendations,- the priority and due date is not.

4 applicable.

l.

8.4.7 Determine -and check the type of violation (H.P.,J Non-H.P.) as-follows:.

p i

l (1) Area Posting Area improperly posted.-

t H.P.

Area boundary. signs.and/or lines down.

~

Non-H.P.

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' Date 1/86' Page R/3-8.

(2) Personnel Exposure Control

i Exposure records incomplete.

~

H.P.

Workers' entered areas without dosimetry or.

Non-H.P.

i violated the posted requirements.:

(3) Radiation Work Permits Failure to enter:available exposure of-H.P.

worker, failure to enter-radiation / contamination levels or. failed to sign the RWP.

Failure to initial RWP or' enter 5the initial Non-H.P.

dosimeter readings. -Failure to be in.

compliance with RWP requirements.-

~

(4) Rad 1oactive/ Contaminated' Material Control-t Improper labeling of bagged contaminated

~

F H.P.

material.

i Non-H.P.

Contiminated material left: lying around in.

a RCA.

8.4.8 Enter the responsible supervisor's name,-then sign and date the.

form.

8.4.9 Obtain the signature of the acknowledging station representative.

8.4.10 Distribute the appropriate copies (per paragraph'8.2.8) after--

the exit interview.

8.5 Closing items - Audit Finding Form - Part 2 8.5.1 Health Physics supervision shall indicate tat corrective

~

actions were taken for 'HP" type findings and:the date the corrective action was taken on Part 2.

For "non-HP" type

~

findings, Station Management should assign responsibility for corrective action to the responsible supervisor. Tne

~

responsible supervisor'shall indicate what reasonable. steps are taken to prevent a recurrance. Any planned' station-superintendent actions should be: addressed on Part 2A.'

~

3.5.2 The Station Superintendent and Station Services Superintendent' should then review and approve the corrective. actions'taken.

4 Corrective actions for POSL and NUDL Audit / Assessment findings.

4 should be reviewed and approved by,the Manager-Production and Operation Services and Supervisor,' Radiological Protection Section,.RAB, respectively.

3.5.3 The form should then be filed such that the auditor. may close

~

them out in the subsequent audit.

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8.5.4 The auditor should review the corrective actions taken to l

ensure that they have1been. completed and that-their completion E

has resulted in satisfactory results._ If_so,:the item may be closed.. Items should not be closed if the stated corrective.

action will be' adequate when completed,_but is_not,'at the time of the audit, totally complete.

i 8.5.5 After thecitem is' closed by.the aud 4or,'the' Audit' Finding Form will be-submitted to-the Supervisor, Radiological Protection Section, RA8 for completion of Part 3.

i 8.5.6 Copies of the completed form will then be distributed-to all.

who received the original audit report (see paragraph 8.3.10).

8.5.7 If.the station (s) determine that a need exists forlan extension-l '

be made by phone or in writing preferably prior to'the due date' on a corrective action due date, a request for extension should

~

i to the Supervisor, Radiological Protection-Section, RA8.' The i

extension.will be approved when the Sopervisor,= Radiological

~

4 Protection _Section, RA8_ agrees'witn the information presented in the request.

In all'other cases, the originalfdue date-shall remain in effect.

~

f 8.5.8 Unresolved disputes concerning audit findings or corrective.

j action shall be identified by the Supervisor,. Radiological

[

Protection, in writing to Manager, RAB, Director of. Nuclear-Engineering, Vice. President of. Nuclear and Environmental Engineering and Vice President Nuclear Operations.

i g

8.6 Audit and Appraisal Trackin'q and Reports l

8.6.1 An annual compilation of audit findings wil'1 be' maintained for i each site. As a minimum, this compilation will include an...

indication of the number of times each category from Table ~l 4-was audited during the calendar year and the number of audit.

items identified for each category. ~This compilation should be i

updated at least quarterly by the Supervisor, Radiological l

Protection Section, RAB.

8.6.2 A review and sunenary of this compilation _ and 'of the' audit.

findings should also be performed quarterly'and used to deter-mine if there are any significant or recurrent health physics

l problems. These problems should_be reviewed with the station,

' f

}.

prior to inclusion in ~ the sunenary,. to ensure-that only ;

uncompleted items.are included. This quarterly susunary rev,iew.

shall be issued by the Supervisor, Radiological Protection 1-Section, RAB and distributed to senior station management and-l

enior NUSCO NE&O management.

1 L

8.6.3 These compilations and sunenaries should be sent to those t

individuals 1isted in Section 8.3.10.1-(excepting' responsible j

, supervisor) and the Senior Vice President,: Nuclear Engineering and Operations.

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R2v. 8 Date 1/86' Page R/3-10 8.6.4 A weekly review of the open. findings on file shall be performed by the Training and Audit Section, RAB.

If it is determined-that a station finding enrrective-action is overdue for closcout by a period of ten (10) working days, the' Supervisor,

^

Radiological Protection Section, RAB, shall inform,_by memorandum, the Station Services Superintendent of said overdue 3

closeout.

If it is determined that a station finding is overdue for closeout by thirty (30).iays, the Supervisor, Radiological Protection Section, RA3, shall notify by t

memorandum the Station Superintendent of the overdue finding i

Closeout.

8.7 Appraisals of Health Physics Programs Upnn request by Station Health Physics or RAB management, appraisals of various portions of health physics programs will be performed by RAB staff. These appraisals should provide reconsnendations for programmatic improvements, if needed, and shall be documented in'a memorandum-based report format. The' distribution for said memoranda 1

shall be determined on a case-by-case basis..

9.0 ACCEPTANCE CRITERIA

. 9.1 Audit items should not be closed out until final action is completed. For example, if the Corrective Action states

" Procedure 902/2902 will be revised to include the above requirement", the audit item should not be c.losed until the

\\

procedure has been revised, received PORC approval and has been implemented.

10.0 RECORD KEEPING t

The Supervisor, Radiological Protection Section, RA8 is responsible' t

for ensuring that all records of the audit program are maintained for at least 3 years.

11'.0 CHECK-0FF LISTS / FIGURES / ATTACHMENTS Table 1.

Audit Categories Health Physics Audit Finding Form _

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c.

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Rev. 8 Date 1/86 Page B/3-11 TABLE 1 AUDIT CATEGORIES i

Applicable Audit Category Topics Including But Are Federal Regulations' During.

Number Subject Not Limited To or Technical Specs.

Outages 1.

External Exposure Exposure Limits, NRC Forms 4 & 5 20.101, 20.102 Control Exposure Updates, HELFORE Accuracy,.

20.104, 20.401 Lost Dosimeter Reports, Exposure to visitors, minors, and pregnant woman Yes 2.

Dosimetry Film /TLD and Dosimeter QA, 20.202 Beta. Dosimetry, Neutron Dosimetry,

^

Extremity Monitoring Yes 3.

RWPs Completeness and adequacy of RWPs, personnel compliance with RWP, Yes' RWP adequate for ALARA requirements 4.

Dose Rate Surveys Adeqdacy and accuracy of surveys, 20.201 routine & job required, Beta Dose

. Rate Surveys, Neutron Dose Rates, Procedures for use of survey instruments Yes 5.

Area Postings Postings' comply'with requirements, 20.202, 20.203 -

Proper Signs, Ropes, Labels, High CY T.S-6.13 Rad Areas locked or controlled MP T.5-6.12

'Yes

6..

Area Contamination Smear Surveys, Area Decontaminations, _

20.201, 20.203 Control check clean areas for. contamination, Alph'a surveys, change area layout.

Yes 7.

Personnel Contamination Protective Clothing - Adequate for_

. Control job, worn properly.. removed properly, rad levels.of clothing in racks, frisking procedures, frisker locations:

and response, documentation of personnel li _ ' ;

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i Rev. 3 Date 1/86 Page 8/3-12 TA;LE I (Cont'd)

Applicable.

Audit Category Topics Including but are Federal Regulations During Number Subject Not Limited To

,or Technical Specs.

Outages 8.

Radioactive Equipment properly bagged and 20.201. 20.203 Material Control frisked, bags, boxes and barrels properly labeled and stored, clean trash checks,

Yes i

9.

Airborne Control Adequate Air Samples Taken -

20.103, 20.203 Breathing. Zone, Particulate, i

Iodine, Gas, Tritium, Alpha MPC Determinations, CAM Opera-tion, Determination of Airborne Areas Yes 10.

Respiratory Protection Inventory and Maintenance of 20.103 Respirators. Proper Use,.Contamina-1 tion levels of respirators, protection factors applied, use for welding,.

cutting, etc.

Yes i

11.-

Internal Dosimetry Stay-Time logs, MPC Hour Calculations, 20.103 j;

mole-Body Counts.:Urinaysis, Fecal Analysis, Nasal Smears Yes.

4 12.

' Portable Instrument Accuracy of calibration sources'and'

. Calibration geometry, calibration of portable dose rate meters and count rate meters, portable air samplers.. neutron monitors, Beta monitors,> Alpha monitors,' Portal-monitors, Lapel Air Samplers.

2

~

13.

Source Inventory &

~All sources accounted for and. leak LSy-product-License Leak-Tests tested at required frequency, smear and counting procedures' adequate j

_. ___ k., _1 __. _.

bv Rev. 8-Date 1/86 Page B/3-13 TABLE I (Cont'd)

Applicable Audit Category Topics Including but are Federal Regulations During.

Number Subject Not Limited To or Technical Specs.

Outages 14.

Radioactive Shipments Procedures and Documentation comply 20.205, 30.41 with all applicable regulations of 10CFR71, 49CFR 10CFR and 49CFR for shipment and 10CFR20.311 receipt of Rad Material 10CFR61 l

15.

Counting Room Propei use and calibration of all Instrumentation counting room instrumention, interpretation of results, H-3 analysis 16.

ARMS, CAMS Locations adequate to protect personnel, operating properly, routine checks, calibrations, alarm response 17.

ALARA Procedures Required hlARA reviews for high exposure jobs, compliance with Corp.'ALARA Program, compliance with Reg. Guides 8.8 & 8.10

.Yes 18.

Training Worker Training - HP and Respiratory, 19.12 HP Staff - Qualifications and Training Rentas Techs.'- Qualifications and Training s

19.

Reports.and Exposure reports upon termination 19.11, 19.13 Notifications or request, annual NRC Reports, 20.401, 20.405 to Workers Overexposure Reports,. Posting of 20.403, 20.408 necessary forms and regulations T.5-6.9.

20.

Special HP Procedures Containwnt and Drywell Initial Entry, Venting IIcad, Steam Generator Work, etc.

Yes 0.

. L.

O O

O Rev. 8 Date 1/86 Page B/3-14' 4

TABLE I (Cont'd)

Applicable.

Audit Category Topics Including but are F.ederal Regulaticns During NueEr Subject Not Limited To or Technical Specs.

Outages 21.

Record Retention Source leak tests and inventories T.S. - 6.10 and Radioactive Waste Shipment records retained for 5 years. Per-t sonnel Exposure Records and Radia-i tion and Contamination Survey records retained for life of tlua license.

Yes i

22.

Iodine monitoring in Vital Areas T.S. - 6.15 under accident conditions.

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Rev.

h-Date 1/86-l'a xe P,/ 3-15 Health Physics Audit Finding Form *

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Pa rt I:

Documentation and Identification of Responsible Supervisor A.

Finding

Description:

Findina Number:

Auditee:

CY, MPl. MP2, MP3, MP1,2,&3, POSL,'NUDL B.

Classification:

- 0 Noncompliance I - Violation of a Noncompliance II - Viotation of a Deficiency 0 Recommendation Immediate Actions Taken (if required) and Priority of Corrective Actions:

C.

1.

Immediate' Actions Taken O

O If yes, detail' actions below:

(NOTE: A Noncompliance I Y

N requires a Yes) 2.

Corrective Actions Priority:

0 *4ithin 1 working day 0 Short-term days O Long-term months.

Corrective Actions Due by:

-Date Auditor Date D.

Finding Type and Responsibility:

~

(,/

O H.P.

O Non-H.P.

Responsible Supr.:

E.

Acknowledgement:

Station Representative Date Part 2:

Corrective Actions Documentation and Management Review A.

Carrective Actions Taken:

B.

Date of Corrective Actions:

Responsible Supervisor Date t

C.

Reviewed by:

Station Ser. Supt.

Date

. Station Superintendent Late

' l i

D.

Auditor Closeout:

. Auditor Date Part 3:

Management Overview Supr. Rad. Prot. Section/ Manager, RAB (C}

REl'EREN CE: Corporate ALARA Mbnual, Part B, Procedure #3

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NORTHEAST UTILITIES' f

CORPORATE MANAGEMENT PROGRAM FOR-MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS.

REASONABLY ACHIEVABLE j

i PART B I

PROCEDURE #4 ALARA DESIGN-REVIEWS 1

O Reviews Completed and Conuments Resolved I

cv

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Manager, Radiologicd Assessment Branch, NUSCO-Procedure Approved af N

g Senior Vice Pre'sident, Nuc)cc:- Eng. & Opers.,

NUSCO,-NNECO, CYAPCO s/24/ev

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Date 4

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Rrv. 2 Date 9/83 Page B/4-1

[

g 1.0 PURPOSE To provide the method, establish the authority and delineate the responsibilities to ensure that ALARA design considerations are exercised and documented at the earliest point in-the engineering design, equipment selection and procuremert process.

2.0 APPLICABILITY 2.1 This procedure applies to all aspects of the design, selection, and procurement of equipment thec contribute to personnel radiation exposure.

2.2 This procedure applies to all personnel, involved in the design, selection and procurement of equipment that will be used or installed in station radiological control' areas.

3.0 REFERENCES

3.1 Regulatory Guide 8.8, "Information Relevant to Insuring that Occupational Exposure at Nuclear Power Stations will be as low as Reasonably Achievable".

3.2 Code of Federal Regulations 10CER20 " Standards for Protection -

Against Radiation".

()

3.3 Nuclear Engineering and Operations Procedure No. 3.03 "Prepara-tion, Review and Dispositien of Plant Design Change Requests (PDCRs)."

3.4 Corporace Management Program for Maintaining Occupational Exposures ALARA, Procedure No. 2 " Occupational Exposure "ALARA" Comparative Cost / Cost Benefit Evaluations."

4.0 DEFINITIONS None 5.0 RESPONSIBILITES 5.1 Director, Generation Engineering', NUSCO shall be responsible for ensuring that those personnel involved in equipment design, selection and procurement consider its radiological impact during installation, operation and maintenance.

5.2 Manager, Radiological Assessment Branch, NUSCO shall be respon '

sible for providing radiological assistance, if necessary, to -

NUSCO personnel engaged in the design, selection, and procurement.

oi equipment to be sed or installed in station radiological control' areas or equipment that will create a new radiation area.

(,)

5.3 station Servican suparintendent shall be responsible for 1-providing radiologicalsassistance, if nedessary,' to station :

4

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9

Riv. 2 Date 9/83 Page B/4-2.

fb personnel engaged in-the ' design, selection and procurement of

's- / -

equipment to be used orl installed in station radiological conttol areas or equipment that will create a new radiation area.

5.4 Personnel engaged in the selection, design and procurement of.

~

equipment to be used or installed in station radiological control areas shall be responsible for ensuring that the equipmeat addresses ALARA~ design criteria.

l 5.5 ALARA Personnel, ' Radiological Assessment Branch, NUSCO, shall i

be responsible for reviewing ALARA Design. Review Checklists,

~ l, completed at NUSCO, and, if necessary, assisting

.in the completion of these checklists.

5.6 Unit ALARA Coordinator shall.be responsible for reviewing ALARA Design Review Checklist,. Attachment 1_ completed at the-Unit l

and, if ascessary,L assisting in the completion 'of, these check' _sts.

6.0 PREREQUISITES None

)

7.0 PRECAUTIONS j

No'ne w

8.0 INSTRUCTIONS 8.1 Personnel engaged in the selection, design and procurement, of either new or replacement equipment shall perform'an ALARA Design Review as early as possible to ensure that the equipment.

l meets the intent of the ' ALARA program.

8.2 All Project Assignments and Plant Design Change Requests should be evaluated by the responsible. engineer to detensine whether or not'an ALARA Design Review'is required. The three questions on the first page of Attachment 1 should assist in making this -

. l.

evaluation. A "yes". answer indicates that an ALARA Design

. Review is required. Indicate the response to these questions.

i 8.3 All existing ' facility and equipment' design modifications, and all new facilities and equipment that meet the_ criteria of Section 8.2, shall be reviewed using the ALARA, Design Review

- l'i Checklist, Attachment 1.

8.4 Attachment 1, the ALARA Design Review Checklist, has been l'

prepared in sections-to facilitate design' review. _The~ sections are:

1.

Location, Radiation Levels and-Shielding

~'

2.

Maintenance, Operation, and Other Considerations

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3.

Piping Systems and Valves.

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4.

Tanks, Sumps and Pumps 5.

Instrumentation q

6.

Filters 7.

Ventilation 8.

Materials of Construction j

i Only the sections that are applicable to the design or modifi-cation un,dey consideration need be used. For example, if only-i

. question 7 is answered "YES", then only Sections 1 and 2 need l

be completed as no new pipes, tanks, pumps, etc. will be installed which will process radioactive material.

Many questions will probably be N/A (Not Applicable) and may be rsswered as such. If a question is applicable, however, in many cases, more than a Yes or No answer is desired. For-example, if the question "Is Shielding 'placed between individual components?" is answered Yes, some discussion should be given.

as to the extent of the shielding and the basis for its adequacy.

8.5 If a design alternative would-increase costs but significantly reduce exposure, perform the analysis described in keference 3.4 to detensine if the alternative is cost effective. This' analysis should be ~ included in the project file.

l 8.6 After the responsible engineer has completed the ALARA Design Review Checklist, it should be reviewed'by ALARA personnel l'

C)

(NUSCO RAB Or Unit ALARA Coordinator depending on whether the PDCR was processed at NUSCO or at one of the operating units).

9.0 ACCEPTANCE CRITERIA The checklists provide guidelines, not requirements. _0ther design requirements or costs may prohibit the implementation of certain applicable guidelines. However, the reasons for not implementing-this particular guideline (s) should be documented on the checklist.

10.0 RECORD KEEPING 10.1 The completed sections of Attachment I should be attached to the PDCR form.

l 1 h. A copy of the first page of Attachment 1 should be retained by

/

ALARA personnel (NUSCO HAB or Unit ALARA Coordinator).

11.0 CHECK 0FF LISTS / FIGURES / ATTACHMENTS.

Attaclueent 1.

ALARA DESIGN REVIEW CHECKLIST j,

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Rev. 2 Date 9/83 Page'B/4 '[

ATTACHMENT 1 y

ALARA DESIGN REVIEW CHECKLIST PA No.

7 j

PDCR No.

Title

.r.

1

~

t Will this project assignment or design change:

require more than one person-res to-install or j

complete?-

-YES/NO i

w

' l Will this' design change create-.a new radiation source or new radiation area onsite'or cause an

. j 3

increase in dost rates from an existing source?-

YES,NO-l i

l Will this design change create or increase routine maintenance, operation, service, or surveillance requirements in a. radiation area? -

YES/NO 1

If any answer is "YES" - complete the applicable sections.

1 Applicable Sections (Circle) 1 2:'3 4 56

'7 8

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i If all three answers are "NO" - no further action is required.

I ALARA Design Review Completed.by-Project Engineer

{

.Date ll Reviewed.by I

NUSCO RAB-or Unit ALARA; Personnel Date l.

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Rev. 2-Date 9/83-Page B/4-5 1

ATTACHMENT 1 ss.

ALARA Desian Review Check'ist Section 1, Location,-Radia. ion Levels, and Shielding 1.

Have recent radiation surveys been reviewed to ensure that locations are selected away_fras hot spots and high radiation areas?

2.

Estimate the radiation levels a.ound the item / component being installed once in operation. Describe each area affected:

3.

Is shielding placed between serviceable components and the substan-i tial radiation source in the area?

4.

Is maximum distance provided between serviceable components an,d the substantial radiation source in the area?-

4 5.

Do design features prevent personnel from inadvertently entering areas where a significant dose could be received in a short period of time? (Check 10CFR20 Requirements) 6.

Is permanent shielding employed to prevent the need' for_ repeated shielding reinstallation?

7.

If permanent shielding is not feasible, are provisions incorporated.

for rapid installation of temporary shielding?

8.

Are shields employed to prevent streasing of radiation through pipe t

and duct penetrations?

~

9.

Are areas of the plant which exhibit high occupancy or are presently 1

uncontrolled adequately protected from new or increased radiation sources?

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- j R;v. 2 Date 9/83 Page B/4-6 l

_ (

m-ATTACHMENT 1

' 3 ALARA Desian-Review Checklist-Seccion 2, Maintenance, Operation and Other Considerations 1.

Has the component or system been selected based on long' service life guarantee, ease of maintenance and operating re ord of low mainte-nance frequency?.

2.

Have reach rnds, special tooling or remote control devices b'een.

l considered?

3.

Has access for maintenance been assessed in component installation?'

+

4.

Have permanently installed platforms, lighting, ladders, etc., been considered for maintenance access and' operation?

5.

Does insulation design allow for rapid removal and replacement (e.g., fiberglass blankets)?

6.

Are components requiring frequent maintenance (e.g. small pumps and valves) designed to permit prompt removal (e.g. flanged connections) to facilitate repairs in lower radiation areas?

7.

Has equipment been laid out with consideration given to facilitating inspections required by 1. tion XI of the ASME Code and other requirements of the ISI program?

1 8.

Can surveillance be performed from outside a high radiation area 2

through the use of remote readout devices, viewing ports, radiation detector ports or TV cameras?

9.

Are provisions incorporated to allow rigging of the component, e.g.,-

pad eyes?

l~

10.

Have periodic maintenance items been eliminated, e.g., "O"

rings, gaskets, packings, protective coatings, lighting components, etc.?

11.

Have lubricating systems or self lubricating units been considered?

12.

Are caten pans, floor and equipment drains and drip pant installed under equipment that have a significant potential for leakage?

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. Riv. 2:

Date 9/83 Page B/4-7 i-_(

ATTACIDENT 1:

ALARA Desinn Review Checklist Section~3,: Piping Systems and Valves i

1.

Are piping run lengths minimized?

i-2.

Are horizontal run-lengths s'inimized?

3.

Are drain-lines sloped continuously and is backflooding prevented?:

i 4.

Is there sufficient flow velocity to prevent settling?

i i

5.

- Are sharp constrictions avoided?.

6.

Are stagnant legs avoided?~

d 7.

Are techniques available to periodically flush, hydsolase or chemi-cally decontaminate piping?

d 2

8.

Are vent lines with horizontal offsets avoided?.

]

9.

Are field joints minimized?

I i=

10.

Are in-line strainers designed fcr optimum system capacity to j-prevent frequent changes?

1 11.

Are check valves included to prevent contaminated fluid backup?

g i

i-12.

Are full ported valves used (e.g., ball valves)?'

7 i

13.

Are valves installed' stem up?..

14.

Have valve designs with bonnet cavities been avoided?.

~

15.

Is quick access to packings provided?

16.

Can the valve motor operator be.quickly removed? ?

17.

Can a-solenoid or motor operator be used 'instead of a man'.tallyy operated valve?

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Rev. 2 Date 9/83 Page B/4-8

' ATTACHMENT 1 ALARA Desian Review Checklist Section 4. Tanks, Sumps and Pumps i

1.

Is the tank or sump located so as to minimize background effects?

l-i i

2.

Is the tank or s'usp bottom sloped to -the outlet?

3.

Is a built in tank spray or sump flush system incl'uded for_ cleanout?

4.

Has curbing been considered to restrict the spread of tank leakage?

Is curbing required to prevent an unmonitored release?

5.

Is the tank's or ausp's interior smooth and free of pockets to facilitate decontamination?

1 6.

Has the use of agitators or mixers to reduce or prevent settling.

been consideced?

~

7.

Have canned pumps or mechanical seals been considered instead of standard packing glands?

s 8.

Are pump seals easily accessible?

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RIv. 2 Date'9/83 Page B/4-9 ATTACHMENT 1 ALARA Desian Review Checklist Section 5, Instrumentation

^

1.

Is instrumentation located in what will be a low background area?

Have remote readouts (or CCTV monitoring) been considered?

3 i

2.

Doestheinstrumentselectedoperatewithaminimum<1uantity-off working fluid?

l 3.

Are transducer pressure ga3es used instead of the bellows type?

i 4.

Is the instrument selected to allow remote calibration?

i-5.

Are in-line flow gauges (indicators) installed to allow easy reading i

from a low dose rate area?

6.

Are instruments grouped fu.tetionally.to minimize time for surveil-lance and calibration?

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R2v. 2 Date 9/83 Page B/4-10 ATTACHMENT l' ALARA Design Review Checklist.

Section 6, Filters 1.

Have filters and other routinely serviced items been standardized?

1 2.

Are filters easily removable?

3.

Have remote or shielded methods for replacement of hot filters' been considered?

4. -

Is cask loading and transport space available?

3 i

5.

Can containssent be established to reduce the spread of contamination during filter changes?

4 6.

Arc. filters located in low occupancy and low traffic areas?

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ATTACHMENT 1

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ALARA Design Review Checklist Section 7, Ventilation 1.

Do ventilation ducts have cleanout ports for' decontamination?

i 2.

Are blower motors located in low-background areas?

1 3.

Do air flows and differential pressures between areas of higher and lower, airborne radioactivity potential prevent flow from high to lower airborne areas?

4.

Are ventilation systems employed capable of being used with systems-for localized control of airborne radioactivity during maintenance operations? (Consider both temporary ductwork attached to existing systems and independent, portable HEPA filtered ventilation systems.)

5.

Are filters for low or non-contaminated ventilation systems located in low background areas?

a 6.

Are filters for highly contaminated ventilation systems located in

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shielded housings?

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Are the materials selected likely to increase the formation of activated corrosion products?

~

2.

Are the materials compatible with primary system chemistry?

3.

Are the materials resistant to radiation effects?

4.

Are rough surface finishes avoided?

5.

Are crevices, holes, notches and recesses avoided?

i 6.

Are sockethead cap screws and knurled finishes avoided?

7.

Are protective coatings selected for the longest possible life expectancy?

j 8.

Are all materials selected for life expectancy of the plant?

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9.

Are concrete snefaces smooth and,ainted for easy deconta.ination, i

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O NORTHEAST UTILITIES CORPORATE MANAGEMENT PROGRAM FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE PART B PROCEDURE #5 ALARA JOB REVIEWS 4

i

O Reviews-Completed and Comments Resolved NKs I

Manager, Radiological As6essment Branch, NUSCO f

Procedure Approved i

Senior Vica) President), Nuclear Eng. & Opers.,

.NUSCO, NNECO, CYAPCO M

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Date ~ ' U i

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Rev. 4'-

Date 8/85 Page B/5-1 To provide the method,, establish the authority and delineate.the responsibilities to ensure that ALARA exposure controls are exercised and documented on jobs within radiological control areas at the nuclear power stations through a systematic program of planning work.

The lead responsibilities for this procedure-lie with the Job / Task Leader, Job / Task Department Head and Station Health Physics Department (Health Physics Supervisor, ALARA Coordinator).

2.0 APPLICABILITY This procedure applies to all aspects of equipment installation, operation, surveillance, modification, repair and maintenance within station radiological control areas.'

This procedure applies to all personnel involved in the planning, supervision, and performance of work in station radiological control areas.

Specific personnel described by title shall mean those personnel or their designated alternates.

3.0 REFERENCES

l 3.1 Corporate Management Program for Maintaining Occupation Exposures I

ALARA, Procedure No. 2, "ALARA Comparative Cost / Cost Benefit Evaluations."

3.2 Corporate Management Program for Maintaining Occupational Expcsures ALARA, Procedure No. 6, " Implementation and Documentation of ALARA Recommendations".

4.0 DEFINITIONS 4.1 Job - All aspacts of Radiation Work Permit (RWP) work associated with the installation, operation, modification, repair or maictuance s

of a component or system. Such work includes but is not linited to:

o Initial job planning in RWP areas.

o Task work (see Task definition).

o Job inspections.

o Cleanup work.

~

4.2 Task - A work package within a Job. Several ~. asks sight be included within a Job. For example, the Jcb covering RCP work could include the following Tasks ' scaffold erection,-insulation removal, decontamina-O tion, component removal, component inspection, component replacement /

repair, etc.

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.Date 8/85 Pase.B/5-2 i-All Tasks within a Job may be tracked by 'a cosuson number assigned to r

i the Job. All RWP's written for the Job can be identified by this number.

i~

4.3 Job / Task Leader - That cognizant member of the station" staff, NU.

System Employee or designated contractor supervisor who is given the y

lead responsibility for the planning, and performance of the Job or-I a Task with.a a Job.

i If a Job is performed by more than one department, the department j

heads will do the rappropriate coordination of the ALARA evaltiations 2

of the Tasks.

~

l The Job / Task Leader may be any one of a variety of personnel, from a l

1ead worker who is given primary responsibility for job organization in the case of a simple job / task to a foreman, engineer or super -

visor for more complex joba/ tasks.

f 4.4 Stop Work Authority - The authority to be exercised by Senior Station Management, on-the-job supervision, Job Leaders or Health l-

+

Physics (HP) staff when radiological conditions / job practices indicate that to proceed might result in conditions that violate NRC

{

regulations, station procedures, or the ALARA controls specified for=

.j the job.

l l

-4.5 Senior Station Manasement - These are the station superintendent, j

unit superintendent (s) and the station services superintendent.

{

4.6 Job / Task Department Heads - These can be Station department heads.,

l NUSCO Supervisors in Generation Engineering, Generation. Construct' ion, Transmission Engineering'and Construction, Interplant Maintenance i

Force, designated Contractor Supervisors.

5.0 RESPONSIBILITIES 1

i 1

l 5.1 Station Superintendents shall be responsible for the effective implementation of this procedure and the strict enforcement of its

-l

}

requirements at the station.

4 l'

5.2 Unit Superinterdents, Station Services Superintendents-and'the f'

i Betterment Construction System Superintendent shall ensure their-personnel are trained in and adhere to this procedure and'are aware i.

of and understand the requirements for ALARA.

In addition, they i

shall ensure ~ that the Department Heads / Supervisors, who are ultimately.

responsible for jobs requiring RWPs, develop 'and provide HP with the -

required information far enough in advance of the start of work to

[

allow sufficient time to implement an effective'ALARA Program, i

\\

j 5.3 Health Physics Supervisor or the ALARA Coordinator 'shall be : responsible.

i for maintaining the necessary systems and records to demonstrate l

that exposures at the station'are ALARA; They.shall be responsible d

for:

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Page B/5-3 l

5.3.1 Assisting the Job / Task Leaders in the performance of ALARA review by providing the necessary current and historical exposure and ALARA records.

(ALARA coordinator).

5.3.2 Maintaining Files on ALARA Job Reviews (ALARA Coo'rdinator).

j-5.3.3 Insuring _that the Job / Task Leader,' Department Head, and when

[

necessary, senior station management.are adequately informed of-significant changes in radiological conditions.

(HP Supervisor / Unit Rad. Protection Supervisor) 4 I

5.3.4 Auditing RWP and ALARA control comnitments to insure they are i

being adhered to by Job / Task Leaders and workers.

(HP Staff /ALARA j-Coordinator) i 5.3.5 Initiating additional ALARA evaluations / controls of Jobs / Tasks j

if actual exposures are becoming more than 20% higher than that l

predicted by the ALARA Job Estimate evaluation.

(ALARA Coordinator) f,,

i l

5.3.6 Performing ALARA Job Reviews with the assistance of the Job /

Task Leader or Department Head and the Station Services Superin -

l tendent.

(ALARA Coordinator) t 5.3.7 Exercising through the MP staff the stop work authority defined in Section 4.0 after proper instruction on its application.

l (HP Supervisor) 5.3.8 Distributing to all Job / Task Department Heads and'the.ALARA f

Coordinator an up to date listing of,their staff's and contractor's exposures on at least a weekly basis and more frequently.during

{

periods of extensive: radiological work.

(HP Supervisor) i a

5.3.9 Completing Attachments 3 and 4, "ALARA Exposure Controls l

Sususary" and "ALARA Post-Job Review". -(ALARA Coordinator).

I 3

\\

l 5.4 Job / Task Leaders and/or Department Heads shall be responsible for:

5.4.1 Reviewing the exposures of their personnel (including contractors) on at least a weekly basis and more frequently during periods of extensive radiological work. Such reviews should use the l

HELPORE_WEXSUM subprogram or equivalent as distributed by the j

station HP department.

l-5.4.2 Completing Attachment I and 2, "ALARA Job Estimate" and "ALARA i

i Job / Task Checklist".

i 5.4.3 Participating in ALARA Job Reviews.

t l

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i l

5.4.4 Ensuring that exposures incurred by department personnel are as l

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evenly distributed as.possible within the.differect skills (crafts).

i 1

H i

I i

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Rev. 4 Date 8/85 Page B/5-4'

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l 5.4.5 Ensuring.that the minimum number of workers needed to do the

]

l job has been determined and that no more than that number has

- i-I been assigned to it.

5.4.6 Ensuring that contractors working for him as Job / Task leaders are adequately instructed in and adhere to this procedure, and to the ALARA controls established on Attachment 3, RWP requirements l'

and all other station written and verbal HP instructions.

l 5.4.7 Ensuring that items listed on the ALARA Exposure Controls l.

Summary, Attachment 3, are available for use and. implemented when the job begins. He shall seek assistance from other station departments /NUSCO engineering if this is necessary.

4-5.5 Manaaer Radiological Assessment Branch (NUSCO) shall be responsible

}

for providing radiological assistance as requested by Job / Task Leaders and HP staff through the Station HP Department as necessa'ry for them to adequately perform ALARA Job Reviews and implement ALARA exposure controls.

5.6 Director, Generation Enaineerina, Director, Generation Projects und

}

Director, Generation Construction (NUSCO) shall be responsible for i

providing engineering assistance as requested by the station Job / Task i

Leaders and HP staff through the Station Engineering Department as necessary for them to adequately perform ALARA Job Reviews and to implement ALARA exposure' controls.

l i

5.7 Radiation Workers (NU system personnel and contractors) shall be responsible for:

j 5.7.1 Keeping their exposures ALARA by remaining knowledgeable in and strictly adhering to the ALARA exposure controls specified in i, RWP requirementa and all other station written -

]

and verbal HP instructions.

)

5.7.2 Keeping their immediate supervisor' informed of their exposures i-so that proper work planning and exposure equalization may be effected.

5.7.3 Notifying their. job supervision and/or HP when it is suspected l

or anticipated that the radiological conditions on the job have or will change.

I 5.7.4 Kaking specific and timely recommendations on ALARA to their immediate supervisor who shall then forward it to the ALARA

[

C:crdinator. Sc: P.cierence 3.4.

t 6.0 PREREQUISITES None.

i 7.0 ECAlffIONS g,

k 1

None.

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Rev. 4

-Date 8/85 Page B/5-5 1-,

8.0 T N_STRUC_TIONS 8.1 JOB PLANNING - Job planning should include procedure reviews, morkup training where possible, special equipment selection,.an on-the-job t.

.(RWP) man hours estimate and person-res estimate as specified below.

8.1.1 For Jobs estimated; by the Job / Task Leader, at less than I'

5 person-res, no formal ALARA review is required. The ALARA Coordinator might, however, specify an exposure control for such work, e.g.,

local shielding, if a preliminary review or.

l-prior experience, warrants it.

0therwise, planning for'such I

work need only address the general RWP radiation protection specifications and instructions for minimizing exposures as determined by the HP Department.

I 8.1.2 For Jobs estimated,-by the Job / Task Leader (s), as greater than j

5 person-rem, the Job / Task Leader (s) shall complete Attachment 1, with the assistance of the unit ALARA Coordinator.

1 i

The number of each of the various type workers needed to do the j

job should be indicated. Job analysis should be performed to i

ensure that only the minimum number of workers needed to efficiently perform the job have been assigned to it.

This information should be attached to Attachment 1.

The Job exposure estimate (in person-tem) shall be made by multiplying the dose rates or effective dose rates in the work area by the estimated RWP man-hours required for completion of l

the job, or by comparison to prior jobs.

8.1.2.1 The estimated RWP man-hours must be based upon the entire Job-duration and not the duration of a single RWP or a single task;

~

8.1.2.2 The work area dose rates should be obtained from HP surveys.

l Alternatively, the effective' dose rate (ares /RWP man-hour) for the task, if done before, can be determined from historical data.

l 8.1.2.3 The sum of the person-res as:sociated with all tasks shall be _

considered as the total person-rem estimate for the Job.

(See definitions of Job and Task, Section'4.0.)

The completion of Attachment 1 will be coordinated by the. Task

]

Department Heads if a Job Leader has not been identified.

}

8.1.3 For Job (s) estimated to exceed 30 person-rem, NUSCO RAB personnel i

should be contacted to provide assistance in the performance of j

the Job Review.

i I

8.1.4 For Jobs estimated, by the Job / Task Leader (s), as-greater than i

5 person-rem, the Job / Task Leader (s) shall complete' Attachment f

2, with the assistance of the ALARA Coordinator.

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1 i

Rav. 4 Date 8/85 Page B/5-6 8.1.4.1 shall be reviewed by the Job / Task Department Heads to ensure the effective consideration and implementation of ALARA.

4 8.1.4.2 Proposed exposure controls can be evaluated for cost-effectiveness using the calculational methods described in Reference 3.5 "ALARA comparative Cost / Cost Benefit Evaluations".

8.1.4.3 A single copy of Attachment 2 can be completed for the entire i-Job or individual task (s) as appropriate, i.e., task might not involve significant radiation exposure or might not have significantly different ALARA requirements.

j i

8.1.5 Att;achments 1 and 2, when completed, are forwarded to the ALARA Coordinator for use in the ALARA evaluation and for future 1

reference.

1 i

8.1.6 The ALARA Coordinator will hold a meeting to' evaluate the ALARA l

exposure controls for the job. 'The meeting may include the Station Services and Unit Superintendents, Health Physics and

' Radiation Protection Supervisors, the ALARA Coordinator and the Job / Task Leader (s) and Department Head as deemed appropriate j

and necessary to perform the evaluation.

i i

8.1.6.1 The members present during this meeting should concur on the l

ALARA exposure controls to be used on' the job. These ALARA exposure controls should be based upon:

(a) a review of prior job history and effectiveness of. any previous ALARA techniques used"on similar Jobs / Tasks I

(b) information derived from the review of Attachments 1 i

and 2, t

j (c) information from other facilities, vendors or industry

.l.

sources.

8.1.6.2, should be used to document both the meeting l

j described above and the ALARA exposure controls to be implemented i

for the Job (Li,st by Job Task, if appropriate).

\\

a)

The originals of Attachments.1, 2,.and 3 are retained by the ALARA Coordinator for reference during the conduct of the Job / Task, the post job review and records retention.

b)

A copy of Attachment 3 is sent to the job / task leader for reference during the job and a copy is sent to HP to

(

permit the HP Technician assignad..to the job or work area

{

j zone to check the job for comp 1.ance with the specified ALARA exposure controls.

8.1.6.3 The ALARA exposure. controls. identified by Att.achment 3 should s

be incorporated into the RWP, Personnel Requirements and Special Instructions or attached to the RWP.

i

-~ - ~-.-

4 Rev. 4-Date 8/85 4

-Page B/5-7 8.1.6.4 The Job / Task Leader shall ensure that the ALARA exposure.

controls'identifie( by Attachment 3 are available and implemented e

v when the job begins.

8.2 WORK PERFORMANCE 1

I 8.2.1 The HP Staff (especially the H.P. Technician covering the job)-

shall audit the job for compliance with the ALARA exposure controls identified in Attachment 3.

i I

8.2.2

'During the perforssace'of a Job / Task, the ALARA C'oordinator-should periodically review.the cumulative exposures to ensure that the ALARA exposure controls are effective.

l l

8.2.3.

The ALARA Coordisator may consider using additional AIARA i

exposure controls if a review as described in 8.2.2 indicates that the person-ree goal may be exceeded..The HP-Supervisor.

i i

and the Job / Task Leader should be contacted to determine if f

~

j such additional ALARA exposure controls-are warranted.

j l

8.2.4 During the course of a Job, (in the' case of jobs estimated at 10 person-res and greater) the ALAPA Coordinator shall notify

}

the Job / Task Department Heads and the Station Services Super-I i

intendent and shall' document the cause on Attachment 4 when the person-res goal is exceeded by 20%.

i 4

8.2.5 The Job / Task Leader shall ensure that all job / task workers are:

i briefed on the work to be performed,

{

.sware of any special tools, procedures and controls to be.

j used before they get on the' Job, and-j have had special training as noted on Attachments 2.

i 8.2.6 The Job Leader / workers or HP Technician coveringLthe job.should j

l inform the HP Supervisor and/or the ALARA Coordinator of.any.

l ALARA controls which in their' estimation are'not being used I

effectively. They should also recommend any controls, procedures, tools, etc. which may be more effective than controls in use once the job had begun.

j f

8.2.7 The Job Leader, the. Job Department Head, HP Staff or the ALARA l

1 Coordinator shall exercise the Stop Work Authority:on the Job i

as defined in'Section 4.0.

This.should occur only if radiological l

conditions / job practices indicate that to proceed might result" in conditions that violate NRC regulations, station procedures-

}-

or the ALARA controls specified for.the ' job.

I When this is exercised, it shall. be immediately coassunicated to all Jcb/ Task supervision and they will resolve the problem.;:If resolu. tion does not occur, senior station management will be s

notiff ed.

In the latter case' resumption;of work shall occur 4

i only after senior station managemet4t has resolved the matter. ;

1 i

i s-

i-R:v. 4 Date 8/85 Page B/5-8 l-I The above process shall be documented on Attachment 4.

S.3 POST JOB REVIEWS 8.3.1 The ALARA Coordinator shall perform a post-job review within

.90 days of a job's. completion for all jobs resulting in five l.

person-res or more.

If the ALARA exposure controls identified in Attachment 3 were j

8.3.2 not implemented or the actual person-rem exceeded that estimated by 20% or more, and at least by 2 person-rem, then a meeting shall be held to determine the cause of the discrepancies. The

]

meeting shall include the Job / Task Leader (s), Job / Task Department Head (s) Senior Station Management, HP personnel and the Unit-l ALARA Coordinator.

4

}

8.3.3 The post-job review must include a quantitative estimate of the person-rem saved and the basis for the estimate.

i i

8.3.4 For repetitive jobs, such as CRD repairs, RCP seal repairs, l

l reactor disassembly and reassembly, refueling, etc., a quantitative comparison must be made between current and past performance.

Exposure trends must be described.

5

)

8.3.5 The post-job review should also describe improvements for future work; reference 3.2 can be used for recommending improvements.

j l

8.3.6 The ALARA Coordinator shall' complete Attachment 4 to document 8.3.1 through 8.3.5.

1 f

9.0 ACCEPTANCE CRITERIA i

None.

10.0 RECORD KEEPING All records of ALARA Reviews will be permanently maintained by the j

ALARA Coordinator. The Nuclear Records facility is acceptable for storage and retrieval.

j 11.0 CHECKOFF LISTS / FIGURES / ATTACHMENTS "ALARA Job Estimate".

"ALARA Job / Task Checklist."

"ALARA Exposure Controls Summary.'_'

j "ALARA Post-Job Review."

l o

4 4

9 s

ATTACHMENT-1 ALARA JOB ESTIMATE

'Rev. 4 l.

Date 8/85.

Page B/5 Job

Title:

Reason for Job:

ALARA No.

A.

List any concurrent work or future work in area which may be coordinated with this job to prevent conflicting conditions and/or duplication of job tasks.

a.

b.

B.

List the number of each of the various type workers needed to do the job..

Include analysis showing that this is the minimum _ number of workers required for efficient performance. Attach list and analysis to this form.

C.

List the job breakdown by expected tasks and subtasks to be performed '

.l'-

including on-the-job (RWP)~ man-hours.

RWP ESTIMATED.

TASK-TASK TITLE SYS/ COMP / JOB /FUNC MAN-HOURS MAN-REM LEADER 1.

2.

~

3.

4.

- i 5.

l 6.

7.

.j 8.

j i

9-4 1

10.

f, 1

Totals

.I Prepared By:

Reviewed by Job Leader or Cosign by Date ALARA Coor.

Date All Task Leaders O.

~

Original: ALARA. Coordinator cc: ' Job / Task Leaders,: Job Task Dept. Heads l

i

I

'l ATTACHMENT 2 ALARA JOB / TASK CHECKLIST Rev. 4

/T Date 8/85 (s,/

Page B/5-10 I

i Job

Title:

Task No. and

Title:

l.-

Has historical data on this or similar jobs been reviewed? Has the.

effectiveness of previous exposure controls been considered?

Describe:

2.

Do the workers have prior experience?

Describe job specific (including mock-up) training.

3.

Describe the following administrative controls:

Schedule for worker briefings on radiological conditions:

Low dose rate worker wait area locations:

Plans for equalizing worker exposures:

Plans for work crew staffing and efficient shift turnover:

i Exposure review point schedule:

i In-process evaluation of exposure controls schedule:

-1 l

l 4.

Describe radiation and contamination source-controls.

f Shielding: (shadow, portable, etc.)

1 Removal of nearby sources:

l

\\

Decontamination:

[

1 \\-l' a

i

__4

Rev. 4 Date 8/85-

/

Page B/5-11 Exhaust ventilation:

\\, /

Tents or glove boxes':

Prefabrication outside radiation area:

Removal of component from area:

5.

Describe efforts to increase job efficiency:

Procedure revision:

Temporary lighting / communication:

l

()

Special equipment / tools:

e Staging /laydown areas-i 6.

High Dose Rate Protection:

Does the work area have the potential for-a significant increase in dose rates, e.g.,

in-vessel, cavity, and TIP rooms?-

~

Has the use of instruments to indicate changing conditions been considered, e.g., alarming doserate meters, water level indicators, etc.?

I 7.

Describe plans for post-job cleanup and waste disposal:

i Prepared By:

Reviewed by' ALARA Coor. Date Job Leader (s) or Dept. Head Date.

i Original: ALARA Coordinator cc: Job / Task Leader (s), Department Head

' i

-a

'~1 Rev. 4 Date 8/85 Page B/5-12 ATTACHMENT 3 ALARA EXPOSURE CONTROLS

SUMMARY

l Job

Title:

Meeting Date:

. Attendees:

Items Discussed:

ALARA CONTROLS TO BE IMPLEMENTED (List by Job or Task as appropriate) l

^

1 I

Prepared by ALARA Coordinator-Name Date Original: ALARA Coordinator cc: Job / Task Leadert's), Departme'nt Head (s), Health Physics e.,

.~

4 Rev. 4 Date 8/85~

Page B/5-13 L -

ATTACHMENT 4 ALARA-POST JOB REVIEW.

c Job

Title:

. Meeting Date:

{

Total Est. RWP Man-Hours:

Total Actual RWP Man-Hours:

I Total Est. Person-Rem:

Total Actual Person-Rem:

~

Attendees:

Previous Exposure:

4 Job Start Date:

Job End Date:

Give estimate of exposure saved by ALARA Controls i

Describe basis of exposure savings estimate:

Has exposure increased / decreased? Explain:

g.

j Could this job be done with fewer people? Explain:

l.

1i j

What problems were encountered that might have increased exposure?

j i

l I

Was anything encountered that made the job easier?

i

.i i

f What would be done differently next time?

-l Reasons for Varying 20% of Goals or Circumstances Behind Stop Work Authority:

r I

i List ALARA items identified in Attachment 3 which were not implemented and justification for not implementing same.

I Prepared by ALARA Coordinator Name Date.

f Original: ALARA Coordinator cc: Job / Task Leader, Job / Task Department Head, Station Superintendent, Services l

Superintendent, Unit Superintendent i

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i NORTHEAST UTILITIES.

CORPORATE MANAGEMENT PROGRAM

-FOR MAINTAINING OCCUATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE i

PART B PROCEDURE #6 l

IMPLIMENTATION AND DOCUMENTATION OF ALARA RECOMMENDATIONS

O 4

Reviews Completed and Comments Resolved Manager - Radi'o hgical Assessment Branch, NUSCO l

i Procedure Approve A Al Senior Vi'ce President, Nuclear Eng. and. 0pers.,

NUSCO, NNECO, CYAPCO I7 h

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Rev. O Date: 4/82 Page B/6-1

~s 1.0 PURPOSF.

4 To provide the method, establish the authority and delineate the responsibilities to ensure that ALARA exposure control and reduction recommendations are documented and evaluated for imple' mentation.

2.0 APPLICABILITY This procedure applies to. recommendations made to help reduce exposure to radiation and radioactive materials. These recommendations may originate from various sources, e.g. outage ALARA reports, vendors and NSSS suppliers, special studies, plant personnel, etc.

This procedure does not apply to routine matters that can be resolved between the radiation workers and Health Physics personnel.

3.0 REFERENCES

3.1 Regulatory' Guide 8.8, "Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be As Low As Is Reasonably Achievable".

3.2 Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposure As Low As Is Reasonably Achiev-able".

3.3 Code of Federal Regulations 10 CFR20, " Standards for Protection Against Radiation".

3.4 Northeast Utilities, Corporate ALARA Program Procedure No. 2,

" Occupational Exposure 'ALARA' Comparative Cost / Cost Benefit Evaluations".

4.0 DEFINITIONS None.

5.0 RESPONSIBILITIES 5.1 The Unit ALARA Coordinator shall estimate the net radiation exposure savings and its amortized value for all ALARA Recommendations.

The ALARA Coordinator shall keep records of ALARA recommendations and associated costs benefit analysis.

5.2 Manager, Radiological Assessment Branch (NUSCO) shall, if requested, provide assistance in the evaluation of ALARA Recommendations.

5.3 The Station Superintendent determines whether au ALARA Recommendation 4

should be implemented or rejected.

6.0 PREREQUISITES O',

~

None.

4 t-I

1 Rev.'O.

Date: _4/82 Page B/6-2 Or

'V' 7.0 ' PRECAUTIONS i

None.

8.0 INSTRUCTIONS I

8.1 The ALARA Recommendation Form, Attachment 1, may.be initiated.

by plant or NUSCO personnel by completing the " Description of Recommendation" and forwarding it to the Unit ALARA Coordinator.

8.2 The ALARA Coordinator shall estimate the net radiation exposure

~ !

-savings and its amortized value using the' methods' described in i

- Reference 3.4, and indicate on the Form:

I a.

Net exposure saving j

i j

b.

Amortized value of the net exposure saving

}

The Form will be forwarded to the Station Superintendent.

)

8.3..The Station Superintendent determines the act' ion to be taken by j.

- either assigning a Controlled Routing to the appropriate Unit / Station Service Superintendent or by rejecting the Recommendation.

Of 8.4 The original Form should be returned to the Unit ALARA Coordinator for record keeping._

i 8.5 The Unit ALARA Coordinator should no,tify. the originator of the status of the recommendation and the. reasons for its' approval a

or rejection.

l 8.6 The Unit ALARA Coordinator should forward a. copy of the completed i.

iors to the NUSCO RAB in order that the recommendation can be i

evaluated for application to other plants.

- i 9.0 ACCEPTANCE CRITERIA i

None, f

10.0 RECORD KEEPING i

1

}

All records of ALARA Recommendations and cost benefit analysis shall i

be maintained by the Unit ALARA Coordinator-for at least five years.

~

The Nuclear Records Facility is acceptable for storage and retrieval.

i 11.0 CHECKOFF LIST

', "ALARA Recommendation and Evaluation Form".

4 i

i 4

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-Rgv. O Date: 4/82-O_

Page: B/6-3 bI ATTACIDfENT 1 ALARA REC 0!!MENDATION AND EVALUATION FORM Recommendation No.

A.

Description of Recommendation Initiator Date Forward to Unit ALARA Coordinator B.

Exposure Savinas Evaluation Net Exposure Saving Amortized Value of Net Exposure Savirg ALARA Coordinator Date Forward to Station Superintendent C.

Station Superintendent i

( ) Implement-Assign CR#

( ) Reject-State Reason

~

Station Superintendent Date

4 1

NORTHEAST UTILITIES

+

CORPORATE MANAGEMENT PROGRAM FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE PART B PROCEDURE #7 REVIEW OF PLANT DESIGN FEATURES AND PROCEDURES I

1 4

]

leted and Comuments Resolved Reviews Comp & h Manager, Radiological Assessment Branch, NUSCO Procedure Approved k, - D. [L1/A

)

Senior Vice Pzhsident,T@ clear Eng. & Opers.

NUSCO, NNECO, CYAPCO Infmb,.

13 lib)~

Date U

1 T

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Rev. 1 Date: 8/85 Page: B/7-1 1.0 PURPOSE To provide the method, establish tr.e authority and delineate the responsibilities for performing a periodic formal revi.ew of the individual plants operating procedures and design features to determine how exposures might be lowered.

2.0 APPLICABILITY This procedure applies to the Haddam Neck and Millstone Nuclear Power Stations.

t

3.0 REFERENCES

5 3.1 Regulatory Guide 8.8,. "Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will i

be As Low As Is Reasonably Achievable."

j 3.2 Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Is Reasonably Achievable."

3.3 Procedure #2, "ALARA Comparative Cost / Cost-Benefit Evaluation."

l

}

4.0 DEFINITIONS 4.1 Design and Procedure Review - This includes a review of operating procedures and past exposure records; plant design features; and consultation with 'the radiation ~ protection staff.

4 5.0 RESPONSIBILITIES 5.1 The Health Physics Supervisor shall be responsible for ensuring that the Design and Procedure Review is performed on at least an annual basis.

5.2 The Unit ALARA Coordinator shall be responsible for generating, j

on at least an annual basis, a list of selected systems, 1

components, work areas and procedures which should be reviewed

}

for methods of exposure reduction.

5.3 The Unit ALARA Coordinator shall be responsible for assisting the Station Superintendent in evaluating recommendations, i

5.4 Station Department Heads shall be responsible for performing the reviews and making appropriate recommendations.

i 5.5 NUSCO Radiological Assessment Branch personnel shall be responsible for assisting in the reviews or the evaluation of j

recommendations, t

Rev. 1 Date: 8/85 j

7-sg -

Page: B/7-2 1

\\]

4 6.0 PREREQUISITES None 7.0 PRECAUTIONS None 8.0 INSTRUCTIONS l

8.1 The Unit ALARA Coordinator shall generate a list of selected l

systems, components, work areas and procedures which should be reviewed for methods / techniques of exposure reduction.

Post-job ALARA review should be examined.

8.2 This list shall be submitted to the Station Superintendent for assignment of review responsibilities to the appropriate Department Heads.

8.3 The assigned Department Heads, should review the item (s) and identify or recommend how exposure reduction might be achieved.

If necessary, this evaluation should use the mothe a described in Reference 3.3.

8.4 The Station Superintendent will evaluate the recommendations made per 8.3 and direct their Lgplementation as appropriate.

The ALARA Coordinator or NUSCO RAB personnel may assist in this 4

t evaluation.

I 8.5 The recommendation implemented and an estimate of the expondre l

saved should be included in the Unit's Annual ALARA Report.

i 9.0 ACCEPTANCE CRITERIA None l

r 10.0 RECORD KEEPING e.'

o,

{

The Unit ALARA Coordinator will retain a copy of the list of items reviewed and the cost-benefit evaluations and recommendations made per 8.3 for five years.

'11.0 CHECKOFF LISTS / FIGURES / ATTACHMENTS 4

None J

f O

4 C,

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O NORTHEAST UTILITIES CORPORATE MANAGEMENT PROGRAM FOR MAINTAINING OCCUPATIONAL EXPOSURES AS LOW AS REASONABLY ACHIEVABLE PART B PROCEDURE #8 ANNUAL AND OUTAGE ALARA REPORTS Reviews Completed and Comments Resolved 1 ll4 lf 2 -

Manager, Radiologreal Assessment Branch, NUSCO Procedure Approved 11A.

Senior Vice President, Nuclear Engineering & Operations NUSCO, NNECO, CTAPC0

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m-R:v. 0 Date: 4/82 i

Page: B/8-1

/7 1.0 PURPOSE

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l To* describe the requirements for and contents of ALARA reports.

2.0 APPLICABILITY This procedure applies to the Haddam Neck and Millstone Nuclear Power Stations and the Radiological Assessment Branch, NUSCO.

3.0 REFERENCES

3 3.1 Code of Federal Regulations 10CFR20, " Standards for Protection Against Radiation".

3.2 Regulatory Guide 8.10, " Operating Philosophy for Maintaining Occupational Radiation Exposure As Low As Is Reasonably Achievable".

4.0 DEFINITIONS None.

5.0 RESPONSIBILITIES 5.1 The Station Services Superintendent shall be responsible for submitting an annual ALARA report and outage ALARA reports, for each operating unit, to the Station Superintendent and the Manager, Radiological Assessment Branch, NUSCO.

5.2 The Unit ALARA Coordinator shall be responsible for preparing an annual ALARA report and outage ALARA reports.

5.3 The Manager, Radiological Assessment Branch, NUSCO sh.ll be t

responsible for compiling the operating unit reports into an annual corporate ALARA report.

6.0 PREREQUISITES None.

7.0 ERECAUTIONS None.

8.0 INSTRUCTIONS I

8.1 Annual Unit ALARA Report 8.1.1 The Station Services Superintendent shall submit an annual ALARA report for each operating unit to the Station Superintendent and the Manager, Radiological Assessment Branch, NUSCO for compil.2 tion into r.n -

annual corporate ALARA report in accordance with the corporate ALARA program.

R;v. O Date: 4/82 Page: B/8-2 8.1.2 I )'.

The Annual Unit'ALARA Report shall contain the D

information described in Attachment 1, " Outline for Annual Unit ALARA Report".

8.2 Outane Reports.

8.2.1 The Station Services Superintendent shall submit an outage report for each outage with greater than 50 person-rem cumulative exposure to the Station Superintendent and the Manager, Radiological Assessment Branch, NUSCO.

8.2.2.

Each Outage Report shall contain the information described in Attachment 2, " Outline for Unit Outage ALARA Report".

8.3 The annual corporate ALARA report shall be prepared by the i

Radiological Assessment Branch,. NUSCO and shall contain the following sections:

8.3.1 Introduction 8.3.2 Executive Summary i

8.3.3 Progress Reports Millstone Station Haddam Neck Station NUSCO Radiological Assessment 2

8.3.4 Exposure Trends, Analysis of ALARA Data 8.3.5 Future Actions and Recommendations 9.0 ACCEPTANCE CRITERIA None.

e 10.0 RECORD KEEPING i

The RAB shall permanently retain a copy of the Annual Corporate ALARA Report.

i 11.0 CHECK 0FF LISTS / FIGURES / ATTACHMENTS i, Outline for Annual Unit ALARA Report., Outline for Unit Outage ALARA Report.

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Rev.

O Date: 4/82 Page: B/8-3 ATTACHMENT 1 OUTLINE FOR ANNUAL UNIT ALARA REPORT 1.

Introduction Describe the status of the ALARA program in terms of its ability to accomplish its purpose or goals. Note any changes in staffing.

2.

Summary Describe the major events and accomplishments of the past year.

Describe any new specific ALARA controls that were initiated and their effectiveness as measured in person-rem reduction.

3.

Exposure Summary Include the total person-rem exposure.

Provide an exposure summary for major jobs performed auring normal operation and the outage (include unscheduled shutdowns). Note and comment on any exposure trends.

For major jobs performed during normal operations, provide details as per Section 2 of Attachment 2.

4.

Future Plans, Describe your goals and objectives for the coming year.

Include a listing of significant ALARA modifications under review, e.g.,

procurement of reactor head shield, hydrolazing equipment, installa-tion of permanent work platforms, etc.

Describe recommendation for reducing exposure or improving the ALARA program in the future.

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ML20203J211

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