ML20237B972

Rev 1 to Procedure Npdap 2.14, Fitness-For-Duty for Duquesne Light Employees

ML20237B972
Person / Time
Site:	Beaver Valley
Issue date:	03/19/1998
From:	Edwards E DUQUESNE LIGHT CO.
To:
Shared Package
ML20237B958	List: ML20237B961 ML20237B967 ML20237B972
References
NPDAP-2.14, NUDOCS 9808200131
Download: ML20237B972 (600)

Text

. 1 RTLCAS.3008 DUQUESNE LIGHT COMPANY l Nuclear Power Division Administrative Manual Unit 1/2 NPDAP 2.14 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES Revision 1 NSRB/OSC Date:

4 Meeting # k[-2d / 3 - / 7~ 7[

Date:

OWNER Approval s ]~/f-ff Date:

Division Vice President y j7 7 i

Nuclear Operations & Plant Manager i

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l Effective Date of Procedure 3-27-98 9908200131 990817 PDR ADOCK 05000334 V PDR l

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Nucl:ar Pow r Division Administrative Manu;l NPDAP 2.14 I Revision 1 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES

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CONTENTS

1. P U R P O S E . . .... . ......... ........ .... ..... .. . ..... ....... . ....... . .. .. . . . . . . . . . .....1 II. APPLICABILITY.. ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . ....1 Ill. RESPONS!BILITIES . . . . . . .. . . . . . . . . . . . . . .. .. . . . . . . . . .......1 IV. I N STR U CTI O N S . .. . . .. . . .. ...... . .. . . ... . . .. . .. . . . . . . . . . . . . . . . . ..................3 A. Fitness-For-Duty .. . ......... .. .. ... ... . .. . . . . . . . . . . . . . . . . . . . . . ... . . . . . . . . . . . ... 3 B. Possession or Use of Alcohol or Drugs on the Job... ....... . .. . . .... ......4 C. Possession or Use of Drugs Off the Job... ... . . . . . . . . . . .. .. . . .6 D. Drug and Alcohol Testing Guidelines . .... . . .. . . .. .. . . . . .........6 E. Rehabilitation / Disciplinary Actions... ...... .. ....... . . .. .. . ... .. . . . . . . . . . . . . . . . . . . . . .9 F. A p pe al s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....................11 G. Continuance Provision ..... ......................... . . . ......... .. . .. .....................12 H. Testing Procedure Actions .. ... ....... . . . . . . . ........................................12 V. REFERENCES.. . . .... ... .......... . ... .... . . . . . . . . . . . . . . . . . . . . . . . . ...........13 VI. CHRONOLOGY OF CHANGES.. ...... .. . ..... . .. .. .. . . . . .............13 Vll. ATTACHMENTS . ..... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ...........13 l

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Nuclear Powsr Division Administrative Manu21 NPDAP 2.14 Revision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 1 of 44

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1. PURPOSE The Company recognizes that the use of alcohol and/or drugs by employees, both on and off duty can affect their ability to perform their required duties. The Company's objective in implementing this procedure is to provide reasonable assurance that Company personnel requiring unescorted access and who MAY be required to report to the Technical Support Center (TSC) or Emergency Operations Facility (EOF) for emergency plan duties are reliable, trustworthy and not under the influence of any substance, legal or illegal, or mentally or physically impaired from ariy cause, which in any way adversely affects their ability to safely and competently perform their duties. This Fitness-For-Duty procedure is intended to establish an environment which is free of drugs and alcohol and the effects of such substances. In addition, an Employee Assistance Program is provided to all employees and is designed to achieve early intervention and provide for confidential assistance. Specimens collected SHALL be used only for the purpose of satisfying ihe  :

requirements of 10CFR Part 26. '

It is the expressed intent that nothing in the revision of this procedure changes the scope and implementation of the Fitness-for-Duty Program for Duquesne Light Employees as (1

established by the application and interpretation of the original Nuclear Group Directive No.

- 45, Fitness-For-Duty Program and implementation Procedure for Duquesne Light Employees dated 1/2/90 (Attachment 4),

11. APPLICABILITY t

This procedure applies to all Company personnel requiring unescorted access t,o protected areas, and also to personnel who MAY be required to report to the TSC and EOF in accordance with emergency plans and procedures. This procedure does not apply to NRC l employees, law enforcement personnel or Offsite emergency fire and medical response l personnel while responding Onsite.

l 111. RESPONSIBILITIES A. The President Generation Group and Chief Nuclear Officer is responsible for the overall implementation of this procedure.

NPDAP 2.14 Nucle r Power Division Administrative Manual Revision 1 Page 2 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES )

B. The Manager, Employee Relations is responsible for the detailed implementation and administration of this procedure, and is identified as the Fitness-For-Duty (FFD)

Program Manager throughout this procedure. The Manager, Employee Relations is also responsible for ensuring that the Employee Assistance Program provider is aware of their responsibility to inform the Duquesne Light Company Medical Review Officer / designee when a determination has been made that any individual's condition constitutes a hazard to himself/herself or others (including those who have self-referred). l C. The Medical Administrator and his/her staff are responsible for conducting Fitness-For-Duty testing.

D. The Medical Review Officer is responsible for reviewing test results and examining alternate medical explanations for any positive test result.

E. Supervisors are responsible to assure all personnel under their supervision are fit-for-duty. l l

F. All personnel with unescorted access or who are assigned to duties under the Emergency Plan requiring access to the TSC or EOF are responsible to report to supervision any person on site reasonably suspected of being unfit for duty, or involved in the use, possession or delivery of alcohol and/or drugs while on duty or on

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Company property.

G. All on-the-job personnel are responsible to report to the Medical Administrator or his/her designated representative when requested for random testing.

H. All personnel SHALL abstain from the use, sale or possession of illegal drugs at all times and abstain from the consumption of alcohol for a period of at least five (5) hours preceding the start of a scheduled work tour and during the period of any working tour.

I. The DLC Nuclear Security Department is responsible for the implementation of security related measures which includes withdrawing or denying unescorted access, assisting supervision in the removal from the workplace of those personnel found using ,

or possessing alcohol or drugs, and performing breath analysis tests (as required). J l

The Nuclear Training Department is responsible for the implementation and verification j J.

of the successful training and periodic re-training of supervisors and all other Duquesne Light Company employees who are subject to the Fitness-For-Duty Program. All Nuclear Power Division management personnel (non-bargaining unit) f SHALL be considered as supervisors for training and re-training purposes.  !

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Nucisar Powar Divition Administrative Manual NPDAP 2.14 Revision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 3 of 44 DUQUESNE LIGHT EMPLOYEES ,

IV. INSTRUCTIONS A. Fitness-For-Dutv

1. Supervisors SHALL assure that all personnel under their supervision are fit-for-duty and are capable of perforrning their required work assignments.

Note: This includes not being under the effects of drugs (e.g., alcohol, prescription, over-the-counter drugs, and illegal substances) and mental stress, fatigue, and illness.

2. Supervisors SHALL inquire during call-outs if the employee has abstained from the consumption of alcohol at least five (5) hours preceding the start of scheduled work. If the employee acknowledges consumption of alcohol within the five (5) hours preceding the start of scheduled work and refuses the call-out assignment, the employee SHALL not be required to work.

3. If the employee does report for an unscheduled working tour and has acknowledged that he/she has consumed alcohol within the five (5) hours preceding the start of work, he/she SHALL be required to submit to a breath

( analysis test. If the test result is equal to or above the 0.04% BAC, or if the employee is deemed to be not fit-for-duty, the supervisor SHALL not assign the employee to work.

4. All personnel with unescorted access or who are assigned to duties under the Emergency Plan requiring access to the TSC or EOF SHALL report to supervision any person on site reasonably suspected of being unfit for duty.

5. When any supervisor has been told or suspects that an employee is not fit-for-duty (whose speech, physical or mental behavior is considered to be aberrant) he/she SHOULD take the following actions:

a. Have at least one other supervisor, if available, observe the employee's behavior,

b. Question the employee in an attempt to determine the reason for his/her abnormal behavior.

1) All observations and discussions SHOULD be documented.

2) If a union employee requests representation, the supervisor SHALL comply.

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c. Review the situation with his/her supervisors or other responsible department or Division personnel to determine what course of action is to be taken.

1) In all cases, the Fitness-For-Duty Program Manager and/or designee SHOULD be consulted by either the employee's supervisor or the supervisor observing the unfit behavior. {

d. If the employee's behavior indicates the possibility of drug abuse and/or alcohol consumption, immediately escort employee to Onsite medical personnel. In the absence of Onsite medical personnel, the employee SHALL be escorted to the Nuclear Security Shift Supervisor for a breath analysis test and the Beaver County Medical Center for urinalysis.

e. If the employee's behavior does not indicate the possibility of drug abuse and/or alcohol consumption but is deemed to be unfit for duty, send or have the employee taken home, or if the problem warrants, taken for medical attention.

f. The Manager, Nuclear Security SHALL be notified by either the employee's supervisor or the supervisor observing unfit behavior to withdraw unescorted f

access.

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g. Advise the employee that he/she is not to report for duty pending further investigation, and that he/she SHALL be contacted at a later date concerning when and where to report.

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h. Review with the employee that an Employee Assistance Program is available for assistance to resolve a family or personal health problem that may be affecting his/her job performance.

Note: Keep in mind the four key elements of supervisory intervention:

Identification

- Confrontation

- Referral

- Treatment B. Possession or Use of Alcohol or Druos on the Job

1. All personnel with unescorted access or who are assigned to duties under the Emergency Plan requiring access to the TSC or EOF SHALL report to supervision any person on site involved in the use, possession or delivery of alcohol and/or drugs while on duty, or on Company property.

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2. When a supervisor has been told or observes the use or possession of alcohol or drugs by an employee on the job or on Company property, he/she SHOULD take the following actions:

a. Contact the DLC Nuclear Security Department for assistance.

1) If possible, confiscate the alcohol or dnJgs immediately.

2) As applicable, request assistance from other supervision in the confiscation and the follow-up investigation.

b. As soon as possible question the employee as to whether or not he/she is using or is in the possession of alcohol or drugs.

1) If a Union employee requests representation, the supervisor SHALL comply.

2) All observations and actions, including the date, time, and personnel involved SHALL be documented by a supervisor.

3) Investigations involving searches of the property, the employee and his/her personal possessions, including lockers, tool chests and vehicles on Company property MAY be conducted for the purpose of detecting possession of alcohol or controlled substances. The results of these investigations / searches and all facts / statements concerning the incident SHALL be documented by a supervisor. The supervisor SHALL request appropriate Union participation when searches involve Union personnel.

c. Review the situation with his/her supervisors or other responsible ,departroent or Division personnel to determine what course of action is to be taken.

1) in all cases the Fitness-For-Duty Program Manager SHALL be consulted as soon as possible.

d. If the employee was observed in the use or possession of drugs and/or alcohol, immediately have the employee escorted to Onsite medical l I

personnel, or in their absence, escort them to the Nuclear Security Shift ,

Supervisor for a breath analysis test and then to the Beaver County Medical Center for urinalysis.

e. Request guidance from the Manager, Nuclear Security concerning additional searches, notification of law enforcement personnel, and disposition of the items confiscated if drugs are involved.

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f. The Manager, Nuclear Security / designee SHALL be nohfied by either the employee's supervisor or the supervisor observing unfit behavior to immediately withdraw unescorted access authorization for the employee in question. The Manager, Nuclear Security / designee MAY also take this action independent of formal notification if the situation warrants.

C. P==ession or Use of Druas Off the Job Note: . The use or illegal sale or possession of narcotics, drugs or controlled substances, or the abuse of prescribed substances by an employee who is off duty and off Company property is unacceptable behavior because it may affect on-the-job safety and performance.

1. All personnel SHALL abstain from the use, sale or possession of illegal drugs at all

' times. Such use may result in disciplinary action up to and including discharge and immediate withdrawal of unescorted access authorization

2. The FFD Program Manager and/or designee SHALL ensure that any personnel found to be involved with illegal drugs off duty and off Company property are immediately removed from their job assignment and that authorization for unescorted access is withdrawn in accordance with established DLC procedures.

3. If applicable, retention of an individualin his/her current position SHALL be contingent on the following:

a. The employee SHALL successfully pass such testing as the FFD Program Manager or MRO deems necessary and appropriate to verify continued freedom from drug abuse during a reasonable probationary period.

b. The FFD Program Manager MAY require the employee to participate in the Employee Assistance Program.

D. Drua and AlcoholTestina Guidelines

1. All personnel SHALL abstain from the consumption of alcohol for a period of at least five (5) hours preceding the start of a scheduled work tour and during the period of any working tour.

2. All on-the-job personnel SHALL report to the Medical Administrator or his/her designated representative when requested by their supervisor for random testing.

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3. The following guidelines SHALL be used by the Fitness-For-Duty Program Manager or designee to determine when an employee SHALL be required to submit to drug and alcohol testing.

a. Initial Access Testina All personnel requiring unescorted access to the PROTECTED AREA, and personnel required to physically report to the TSC or EOF SHALL successfully complete chemical testing for involvement with drugs and/or alcohol before such access is initially granted.

Note: Any test, conducted in accordance with 10CFR26 that was done within sixty (60) days of initial access, could be used for granting unescorted access.

b. Random Testina

1) Unannounced tests SHALL be conducted in a statistically random and j unpredictable manner.

2) The test SHALL be administered so that a person completing a test is j

(' immediately eligible for another unannounced test.

3) Random testing SHALL be conducted at an annual rate equal to at least f I

50% of the work force.

c. Reasonable Cause Testinn Note: Every employee who is recommended for a chemical test due to reasonable cause by the employee's supervisor SHALL be reviewed by the Fitness-For-Duty Program Manager and a determination SHALL be made of the appropriateness of such a test before the employee is notified of the testing requirement.

Testing for reasonable cause SHALL be done for reasons listed below; however, they are not all inclusive. The Company MAY test for any illegal drugs during a "for cause test", or analysis of any specimen suspected of being adulterated or diluted through hydration or other means.

1) As soon as possible following any observed behavior indicating possible substance abuse.

2) After accidents involving a failure in individual performance resulting in personalinjury.

3) in a radiation EXPOSURE or release of radioactivity in excess of

( regulatory limits.

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4) Actual or potential substantial degradation of the level of safety of the plant if there is reasonable suspicion that the worker's behavior contributed to the event.

5) After receiving credible information that an individual is abusing drugs or alcohol.

6) Involvement in the use, possession or delivery of a controlled substance or alcohol while on duty or on Company property.

7) Involvement in the use or oelivery of a drug other than a controlled substance while on duty or on Company property without authenticated medical evidence.

8) If alcohol has been consumed within five (5) hours of a required reporting tour of duty resulting from a call-out, only a test for alcohol SHALL be administered.

d. Follow-uo Testina Follow-up testing is required for those personnel known to have tested positive for drugs and/or alcohol at a Nuclear facility. ,

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1) On initial retum to work, personnel who have completed rehabilitative treatment for drug and/or alcohol SHALL provide a urine sample, under observation, for chemical testing to verify continued abstinence from the use of drugs and/or alcohol (except for self-referral).

2) On an unannounced basis, all personnel who have completed rehabilitative treatment for drug and/or alcohol (except for self-referral treatment) or who have tested positive at another nuclear power plant in accordance with a Fitness-For-Duty procedure that resulted in on-duty impairment subject to a plan for treating substance abuse (except for self-referral treatment), or removed from activities or denied unescorted access, as determined by suitable inquiry SHALL be follow-up tested.

3) Any person granted unescorted access or whose access is reinstated .

under IV.D.3.d.1) and IV.D.3.d.2) above, for drug-related treatment SHALL be given unannounced follow-up tests at least once a month for four (4) months and at least once every three (3) months for the next two (2) years and eight (8) months after unescorted access is reinstated.

4) Any person granted unescorted access or whose access is reinstated under IV.D.3.d.1) and IV.D.3.d.2) above for alcohol-related treatment, l SHALL be given unannounced follow-up tests at least once a month for )

four (4) months and at least three (3) times in the next one (1) year and eight (8) months after unescorted access is reinstated.

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e. Unscheduled Workina Tour

1) Employees who have accepted an unscheduled working tour (call-out) and have acknowledged consumption of alcohol within the five (5) hours prior to the start of the scheduled working tour, SHALL be required to submit to a breath analysis.

2) If the result of the breath analysis is below 0.04% BAC, the supervisor SHALL make a determination as to whether the employee is fit to perform the task assigned.

3) If the results are equal to or in excess of 0.04% BAC, the employee SHALL not be assigned to work, and the supervisor SHOULD send or have the employee taken home.

E. Rehabilitation / Disciplinary Actions in the following steps of Section IV.E. the Medical Review Officer / designee SHALL report the test results to the FFD Program Manager / designee. As appropriate, the FFD Program Manager / designee SHALL initiate disciplinary measures and monitor rehabilitation requirements,if applicable.

1. The following actions SHALL be performed if chemical testing results confirm the presence of a drug (Confirmed Positive Test Result):

a. Regular or temporary employees with the presence of a drug (Confirmed Positive Test Results) without authenticated medical evidence verifying medical treatment, as determined by the Medical Review Officer, SHALL result in the employee being relieved from duty placed on indefinite suspension, and unescorted access denied for a minimum period of fourteen (14) days and possibly be subject to rehabilitation procedures which MAY include a residence program. If the employee is retumed to work, they SHALL be subject to follow-up testing.

b. Any subsequent Confirmed Positive Test Result SHALL result in removal from unescorted access to PROTECTED AREAS for a minimum of three (3) years from the date of removal and placed on indefinite suspension pending review. ,

c. Any Confirmed Positive Test Result through the follow-up testing process or any other determination of subsequent involvement in the sale, use or l

possession of illegal substances SHALL result in permanent denial of unescorted access, and the employee placed on indefinite suspension pending review.

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Nuclear Power Divi; ion Administrative Manurl NPDAP 2.14 Rsvision 1 Pcgs 10 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES

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d. If the presence of a drug (Confirmed Positive Test Result)is the result of verified medical treatment, the employee SHALL be permitted to perform his/her normal job functions unless specifically prohibited from doing so by the Medical Review Officer.

e. Employees who are directed to submit to a urinalysis in accordance with this procedure and refuse, SHALL be subject to removal for cause. The employee SHALL be placed on indefinite suspension and denied unescorted access pending review.

f. ~ Employees who are required to submit to urinalysis for reasonable cause, SHALL be placed on a paid leave of absence pending the outcome of the analysis. If the analysis is negative, no record of the leave SHALL be kept. If the analysis is confirmed positive, rehabilitative or, if warranted, disciplinary action SHALL be initiated in accordance with this procedure. The employee SHALL be placed on indefinite suspension pending review.

2. Determination of blood alcohol content to be equal to or in excess of 0.04% BAC by an evidential grade breath tester SHALL require the following actions:

a. The presence of alcohol, equal to or in excess of 0.04% of the blood alcohol concentration, SHALL be cause to relieve the employee from duty, deny )

unescorted access, place on indefinite suspension, and consider initiation of rehabilitation procedures including a residence program with the exception of reporting for an unscheduled working tour (call-out).

b. Any subsequent occurrence of being tested equal to or in excess of 0.04% of the blood alcohol content, the employee SHALL be relieved from duty, denied unescorted access, placed on indefinite suspension pending review, and MAY be subject to initiation of rehabilitation procedures which MAY include a residence program, with the exception of reporting for an unscheduled working tour (call-out).

c. Employees who are required to submit to an evidential grade breath test in accordance with this procedure and refuse SHALL be subject to removal for cause. The employee SHALL be placed on indefinite suspension and denied unescorted access pending review. .

d. Employees who are required to submit to an evidential grade breath test for reasonable cause and request a blood alcohol test for additional confirmation, SHALL be placed on an unpaid leave of absence pending the outcome of the analysis. If the analysis is positive (equal to or in excess of 0.04% blood alcohol concentration), rehabilitation and/or disciplinary action SHALL be initiated in accordance with this procedure.

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e. An employee who reports for an unscheduled working tour, in accordance with Section IV.D.3.e of this procedure and the results of the breath analysis ]

are equal to or in excess of 0.04% BAC on three (3) or more occasions in a current twelve-month period or five (5) or more occasions in a current 36-month period, SHALL be counseled by the Medical Review Officer.

3. Any individual determined to have been involved in the sale, use, or possession of illegal drugs while within the PROTECTED AREA of any nuclear power plant SHALL be denied unescorted access for a minimum period of five (5) years and placed on indefinite suspension pending review.

4. Any individual determined to have been involved in the sale, use or possession of alcohol while within the PROTECTED AREA of any nuclear power plant SHALL be denied unescorted access and placed on indefinite suspension pending review.

5. Any individual who has been denied access for three (3) years or more for the illegal sale, use or possession of drugs and who MAY be requesting unescorted access at the Beaver Valley Power Station SHALL only be granted unescorted access upon receiving satisfactory medical assurance that the individual has abstained from drugs for at least three (3) years. Granting of unescorted access SHALL be contingent upon satisfactory management and medical assurance of I

( , the individual's fitness to adequately perform his/her job duties. In addition, if unescorted access is granted, follow-up testing in accordance with Section IV.D.3.d.3) of this document SHALL be required.

F. Appeals

1. An appeal process SHALL be afforded by the FFD Program Manager / designee to all employees in the following manner. .

a. Upon request of the individual or Union, the split sample SHALL be sent for analysis in accordance with the Implementation Procedure.

b. Management employees MAY utilize the Duquesne Light Company Open Door Policy, No. 305.

c. Union employees MAY utilize the grievance procedure as described in the .

Labor Agreement under Article IX.

2. Any individual who is the subject of a drug or alcohol test SHALL, upon written request to the FFD Program Manager / designee, have access to any records l

relating to his or her tests and any records relating to the results of any relevant laboratory certification, review, or revocation of certification proceedings.

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G. Continuance Provision in the future, legislative, regulatory and/or judicial action by govemmental authority may conflict and invalidate specific provisions of this procedure. In that event, the remainder of the procedure and all provisions not specifically invalidated by such j legislation SHALL remain in effect. In the event technological advances in the analysis present opportunities to improve reliability of results or improve the comfort level of ,

employees required to submit specimens for analysis, this procedure SHALL be j altered accordingly, after full communication and advertising of the changes with the Union and employees.

H. Testina Procedure Actions Attachment 2 is a step-by-step guide on processes that occur while administering the

- applicable test (s). It is utilized by the Medical Administrator and his/her staff.

1. Insofar as specific actions required on the part of personnel selected to be tested (applicant / examinee), the following requirements have been extracted from Attachment 2. Personnel selected to be tested SHALL:

a. Drua Test

1) Provide positive identification.

2) Read and sign a Consent To Testing form.

3) Remove all outer garments (jacket, coat, sweater).

4) Leave purse, brief case or carry bag outside of collection room.

5) Wash and dry hands prior to urination.

6) Urinate directly into container to minimum level of 60 ml.

7) Submit specimen container to Medical personnel.

8) Initial the two evidence tapes, and sign the permanent record book. ,

9) Option to request and pay for analysis of split sample within (3) days of notification of a positive test result.

b. Alcohol Test

1) Provide two breath specimens for each screening.

2) If positive, provide a confirmatory test on another evidential grade breath )

I test device.

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3) Option to request a confirmatory blood test.

a) Initial evidence tape for given blood sample.

2. The Medical Administrator SHALL ensure the results of these tests become a part of the examinee's medical records and/or nuclear access records.

V. REFERENCES ,

A. Federal Register 10 CFR Part 26.

B. Duquesne Light Company, Open Door Policy, No. 305.

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VI. CHRONOLOGY OF CHANGES A. Revision 0 - Revised Nuclear Group Directive 45 for inclusion in the first issue of NPDAM.

. B. Revision 1 - Revised changes in chain of custody form application, corrected typographical errors, clarified the direct observation for certain follow-up tests and added Attachment 3. .

Vll. ATTACHMENTS

1. Consent To Testing Form

2. Implementation Procedure 1

3. Federal Drug Testing Custody and Control Form  !

4. Nuclear Group Directive 45 (s

Nuclear Power Division Admini;trctiva M nu;l NPDAP 2.14 Revision 1 Pcgs 14 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEE 5 ATTACHMENT 1 CONSENT TO TESTING FORM 1,

. do hereby knowingly gree to submit to a breath analysis and to provide a blood and/or urine specimen to Duquesne Light Company and its designated specimen collection agency and/or laboratory and to permit them to analyze my blood and/or urine specimen to detect the presence of drugs and/or alcohol. I give my permission to the designated specimen collection agency and/or laboratory to release the results of the blood and/or urine analysis to Duquesne Light Company.

List ALL the prescription medication and over-the-counter preparations you have taken within the past thirty (30) days.

Examinee is required to sign t;.e Consent to Testing form in accordance with 10CFR26 Appendix A,2.4(g)(4). ,

Signature Date FOR COMPANY USE ONLY 10CFR26 Appendix A,2.4(J)" Failure to Cooperate". If an individual refuses to cooperate with the urine collection or breath analysis process (e.g., refusal to provide a complete specimen, complete paperwork, initial specimen), then the Medical Administrator SHALL report the failure '

to cooperate to the appropriate management.

Reason:

Date:

Time:

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Collection Site Person:

Signature

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ATTACHMENT 2 Drug and Alcohol Testing Implementation Procedure

1. Drug and alcohol testing MAY technologically be administered using multiple analysis methods, however, in order to clarify the procedure for any analysis method selected for implementation, the following specific summary of required actions is presented.

a. Urine, Blood and intoxilyzer Analysis Urine and intoxityzer analysis is a requirement for all personnel requiring unescorted access to the protected area, TSC or EOF in accordance with emergency plans and procedure. To assure strict confidentiality and the utmost control of this procedure, the

- following guidelines SHALL be used in the collection and transfer of the urine and blood (if applicable) to the laboratory.

1) The Medical Staff SHALL establish appropriate procedures in order to assure that the examinee provides an authentic urine sample and accurate breath analysis.

( 2) The examinee SHALL be required to provide positive identification and to read i and sign a Consent To Testing Form (Attachment 1). Refusal to sign the form l SHALL require the drug screen / breath analysis procedure to be terminated and the individual SHALL be handled in accordance with the requirements of Section IV of NPDAP 2.14 (Fitness-For-Duty) or NPDAP 2.9 as applicable.

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3) The examinee SHALL be required to remove all outer garments (jacket, coat, sweater), and SHALL not be permitted to carry a purse, brief case or any type of carry bag into the collection room. If the examinee ,is wearing long sleeves, these SHOULD be rolled up and the examinee SHOULD be visually examined to ensure the examinee cannot access a container previously filled with a foreign substance or a prepared sample. The room used to take the specimen SHOULD not have '

running water, if a room without running water is not available, the water supply valve to the sink SHOULD be shut off and the faucets at the sink SHOULD be opened. Any toilet SHOULD have coloring added to bcth the bowl and tank. This is done so the urine sample cannot be diluted. The examinee MAY be given a  :

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reasoncble amount of liquid to drink if the necessary quantity of urine cannot be provided (e.g., a glass of water). The individual SHALL oe instructed to wash and i dry his/her hands prior to urination.

4) The FFD Program Manager SHALL deny or withdraw unescorted access of an examinee who refuses to provide a urine specimen or breath analysis. The Medical Section or designee SHALL refer such a refusal to the examinee's

(' assigned Unit or supervisor and SHALL notify the Manager, Nuclear Security for appropriate action.

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Nucle,w Pow:r Division Administrative Menu:1 NPDAP 2.14 Rcvision 1 Page 16 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES

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5) The following materials are required:

a) Special" Federal Drug Testing Custody and Control" form (7 parts)

(Attachment 3).

b) Two sealed clean containers for urine.

c) Sterile vacuum tubes and needle assemblies for blood.

d) Two special 5" x 8" Chain-of-Custody bags. One bag for blood. l I

e) Evidence tape.

f) Two evidential grade breath test devices.

b. Urine Collection

1) Two clean specimen containers SHALL be selected by the examinee.

2) Direct observation of the collection process SHALL not be required unless the medical personnelin charge of the collection suspect the examinee is attempting to adulterate or substitute the sample. The Medical personnel SHALL monitor the }

collection process in order to maintain control of the integtity of the specimen.

The examinee SHALL be requested to urinate directly into one container. The container SHALL be filled for a minimum collection of 60 ml.

3) Upon exiting the collection room, the examinee SHALL submit the specimen container to the Medical personnel who, in the presence of the examinee, SHALL initiate a temperature test and as an option MAY initiate a specific gravity test. If the test results verify the specimens are authentic, then the specimen in the container SHALL be divided into two smaller samples for shipment and/or storage.

The examinee SHALL then be requested to initial the evidence tapes and sign tne permanent record book certifying that the specimens collected are in fact the specimens provided by him or her. The containers SHALL then be sealed with the evidence tape in the presence of the examinee. Whenever there is reason to believe that a particular individual MAY alter or substitute the urine specimen to be provided, a r,ecor. i specimen SHALL be obtained as soon as possible under the .

direct observ. tion o' a same gender collection site person. Where appropriate, measures SHAJ se taken to prevent additional hydration.

4) The Medical personnel, or designee, SHALL complete the " Federal Drug Testing Custody and Control" Form (Attachment 3) which includes the time, date, and signature for each specimen container.

5) The specimen, the original, and one copy of the form SHALL be placed in the )

Chain-of-Custody bag and sealed. One copy of the form is kept by the Medical Section.

Nucloir Powsr Division Administrative Manu 1 NPDAP 2.14 Revision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 17 of 44 DUQUESNE LIGHT EMPLOYEES

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6) The Medical Section SHALL retain one specimen container at its facility and maintain the specimen in proper environmental conditions. This specimen SHALL be retained and used as a second specimen for analysis if the first specimen is positive and the examinee or Union requests a second analysis. This request SHALL be made within three (3) days of notification of a positive test result. The cost of the second analysis SHALL be bome by the requester (examinee'or Union) and arraresments for the acceptable payment SHALL be made at the time of the request. 'Ine split sample SHALL be forwarded on the day of the request to another HHS certified laboratory that did not test the aliquot sample. The purpose of the second analysis is to provide the examinee or the Union evidence of the accuracy of the first analysis. If the initial confirmed positive test analysis is not reconfirmed by the second analysis, the overall test procedure SHALL be considered as a negative test result and the examinee or Union SHALL be refunded the cost of the second analysis.

7) The Medical Section SHALL call the courier service for same day urine specimen )

pickup for one of the containers.

8) The Chain-of-Custody bag SHALL not be opened until it is received by the designated personnel at the testing laboratory who SHALL document the integrity of the seat and SHALL place the specimen in locked storage until processing.

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9) The Medical Section SHOULD normally receive the urine drug screen results within twenty-four (24) hours if the results are negative. It may take two (2) days to receive confirmation of positive test results. These times may vary dependent upon the specific laboratory service used for such screening. The laboratory SHALL fumish documentation supporting the credibility of the chain-of-custody as well as the results of the specimen analysis, it is imperative that confidentiality is maintained when the Fitness-For-Duty Program is utilized. All records, results, and opinions resulting from such tests SHALL be kept confidential.

10) The results of the drug screen test SHALL become a part of the examinee's medical records and/or nuclear access records, and SHALL be reviewed on a limited, confidential basis by those Company off".ials involved in administration of physical examinations, drug screens, unescorted access, or disciplinary matters.

When the Medical Review Officer, after final review of results, determines a positive test analysis, he/she SHALL inform the Fitness-For-Duty Program Manager, or his/her designated representative who SHALL be responsible for instituting a review of the individuals employment status and/or unescorted access status. Medical personnel SHALL also inform the Manager, Nuclear i Security or designee.  !

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NPDAP 2.14 Nucle r Pow:r Divisica Administrative Manu 1 Revision 1 Page 18 of 44 FITNESS-FOR DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES )

c. Intoxityzer and Blood Collection

1) Alcohol breath tests SHALL be delayed at least fifteen (15) minutes if any source of mouth alcohol (e.g., breath fresheners) or any other substances are ingested (e.g., eating, smoking, regurgitation of stomach contents from vomiting or burping). The collection site person SHALL ensure that each breath specimen taken comes from the end, rather than the beginning of the breath expiration. For each screening test, two breath specimens SHALL be collected from each individual no less than two minutes apart and no more than ten (10) minutes apart.

The test results SHALL be considered accurate if the result of each measurement is within plus or minus ten percent (110%) of the average of two measurements. If the two screening tests do not agree, the breath tests SHALL be repeated on another evidential-grade breath analysis device. Confirmatory testing is accon 'shed by repeating the above procedure on another evidential grade breati alysis device.

2) If the alcohol breath screen test indicates a BAC result of .01% to .03% and each measurement is within plus or minus ten percent, then the test SHALL be considered accurate. A confirmation test SHALL be initiated on another evidential grade breath analysis device. If the result of the confirmatory test indicates a BAC of .01% to .03% as a test average of the two measurements, the individual SHALL be counseled by the MRO. The individual's Supervisor and Fitness-For-Duty )

Program Manager SHALL also be notified to initiate fitness-for-duty determination.

3) If the alcohol breath screen test indicates the individual is positive for a BAC at or above the 0.04 percent cutoff level, a confirmatory test for alcohol SHALL be done with another evidential grade breath analysis device. If a person demands further confirmation, the test SHALL be a gas chromatography analysis of blood. All vacuum tube and needle assemblies used for blood collection SHALL be factory-sterilized. The collection site person SHALL ensure'that they remain properly sealed until used. Antiseptic swabbing of the skin SHALL be performed with a non ethanol antiseptic. Sterile procedures SHALL be followed when drawing blood and transferring the blood to a storage container, in addition, the container SHALL be sterile and sealed.

4) Upon request of the examinee to have a confirmatory blood test, the Medical -

person SHALL draw a vacuum tube of blood from the examinee.

5) In the presence of the examinee, the vacuum tube SHALL be sealed with evidence tape and the examinee SHALL be required to initial the evidence tape.

6) The Medical personnel, or designee, SHALL complete the " Federal Drug Testing Custody and Control" Form (Attachment 3) which includes the time, date, and signature for each sample container.

Nucle:r Pow;r Division Administrative M: nut! NPDAP 2.14 Rsvision 1 FITNESS-FOR-DUW PROGRAM FOR Page 19 of 44 DUQUESNE LIGHT EMPLOYEES

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7) The sample, the original, and one copy of the form SHALL be placed in the Chain-of-Custody bag and sealed. One copy of the form is kept by the Medical Section.

8) Medical Section personnei or designated representative (NOTE 1) SHALL call the courier service for same day blood sample pickup of the container.

NOTE 1: if the Medical personnel collecting the blood specimen are not Company medical personnel as detailed in following step c.12, then the Duquesne Light Company supervisor in charge SHALL notify the medical authority that the Company Medical Section SHALL notify them as soon as possible but no later than the next work day as to how the specimen SHALL be transported to a laboratory for analysis. The Medical Section MAY at their discretion select the hospital facilities to conduct the collection.

9) The Chain-of-Custody bag SHALL not be opened until it is received by the designated personnel at the testing laboratory who SHALL document the integrity of the seal and security of the sample until processing. It is imperative that confidentiality be maintained when the Fitness-For-Duty Program is utilized. All records, results, and opinions resulting from such tests SHALL be kept confidential.

10) The results of the blood analysis SHALL become a part of the examinee's medical records and/or nuclear access records, and SHALL be reviewed on a limited, confidential basis with only those Company officials involved in administration of physical examinations, drug / alcohol screens, unescorted access matters, or disciplinary matters. When the Medical Review Officer, after final review of results, determines a positive test analysis, he/she SHALL inform the Fitness-For-Duty Program Manager or his/her designated representative, who SHALL institute a review of the individual's employment status and/or unescorted access status.

Medical personnel SHALL also inform the Manager, Nuclear Security or designee.

I

11) If the Chain-of-Custody is violated, the test results SHALL be considered void and a review wi'h the initiating party SHALL be conducted by the Medical Section to determine if another sample SHOULD be obtained.

12) In the event the implementation procedure noted above is not performed by '

Medical Staff, all designated testing functions SHALL apply to the medical representative designated by the Company.

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Nucts:r Pow r Division Admini;tr tiva Manual NPDAP 2.14 R: vision 1 Page 20 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES l

13) Hospital and/or other medical facility listed below SHALL be designated as the location where the blood / alcohol collection MAY be performed as an attemative to

' the Medical Section when they are unavailable. When this location is selected by l the examinee's supervisor as the location for the collection, the supervisor SHALL accompany the examinee to the facility, and present the medical authority at the facility with the medical equipment and instructions to implement the collection procedure and the Chain-of-Custody. The facility listed below has a Purchase Order established with the Company to authorize payment for collections they perform.

Medical Facility: Beaver County Medical Center Address: 1000 Dutch Ridge Road Beaver, Pennsylvania 15009

14) If the Chain-of-Custody is violated, the test results SHALL be considered void and a review with the initiating party SHALL be conducted by the Medical Section to determine if another specimen SHOULD be obtained.

d. Urine, Blood and intoxilyzer Screening Testing Parameters

1) Initial screening of urine and blood specimens SHALL be conducted by a )

Department of Health & Human Services certified laboratory which utilizes a chain-of-custody procedure for all specimens submitted for analysis by the Company.

2) Initial urine screening SHALL be conducted by using an immunoassay method.

3) Initial breath analysis SHALL be conducted by using an evidential-grade breath analysis device that conforms to the National Highway Traffic Safety f Administration Standards (49FR 48855) and any applicable state statutes.

4) The following initial cutoff levels SHALL be used when screening specimens to determine whether they are positive for the indicated substances.

Initial Screen Positive Thresholds Values .

Drua Nanoarams/ Milliliter Marijuana Metabolites 100 Cocaine Metabolites 300

' Opiates 300*

Phencyclidine 25 Amphetamines 1000 Alcohol 0.04% BAC y

• 25 ng/ml is immunoassay specific for free morphine

Nucl:Ir Power Division Administrative Manual NPDAP 2.14 Rsvision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 21 of 44 DUQUESNE LIGHT EMPLOYEES

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e. Urine Blood and intoxityzer Confirmatory Testing Parameters

1) Positive indication for any of the drugs identified in step d. SHALL require a confirmatory test for each drug identified as positive by the initial screen.

2) A confirmatory test procedure for urine and blood, if applicable, SHALL require the use of the Gas Chromatography / Mass Spectrometry method (GC/MS).

3) A confirmatory test procedure for breath analysis SHALL be accomplished by repeating the procedure in step c., on another evidential-grade breath analysis device.

4) Confirmation test analysis SHALL be conducted for the following drugs, as warranted by the initial screening analysis, using the following threshold values as a positive indication.

Confirmation Positive Thresholds Values Drua Nanoarams/ Milliliter Marijuana Metabolites 15*

f Cocaine Metabolites Opiate 150" Morphine 300 Codeine 300 Phencyclidine 25 Amphetamine Amphetamine 500 Methamphetamine 500 Alcohol 0.04% BAC

• Delta-9-Tetrahydrocannabinol 9-Carboxylic acid "Benzoylecgonine l

NPDAP 2.14 Nucle:r Pow:r Division Administrative Manual Revision 1 Pags 22 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES

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Nuclear Power Division Administrative Manual NPDAP 2.14 Revision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 23 of 44 DUQUESNE LIGHT EMPLOYEES

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ATTACHMENT 4 I

oooursur LIcur cowamy NUC1 EAR GROUP rrruzss roa ou9nt nAwuaL REVIEW AND hPPROVAL SHErr TAs: s TITLE: Nuclear Group Directive 45 1

( IsscE Z_ R M SION O EFrECF M DATE 112/90 a m ew: SIGNATURE DATE Medical Section

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t NPDAP 2.14 i Nucircr Power Division Administrative Mcnual Revision 1 l Pcge 24 of 44  ;

FITNESS-FOR-DUTY PROGRAM FOR I

DUQUESNE LIGHT EMPLOYEES suCx m caoue DraECT:vE 30. ss TI" NESS-TOR-DUTT PM0 GRAM AND IMPI.EMElff& TION FJ'?' Tok DUQUESNE LIGHT EMPImYIjE

. renrosE ne campany recognizes that the use of alcohol and/or drugs by employees, both on and ofo duty can effect their ability to perfore their required duties. De Company's objective of this Dir ective is to provide . reasonable assurance that Company pers onnel requiring unescorted access and who may be required to report to the Technical Support Center (T5C) or Esergency Ope *stions Facility (EOF) for emergency plan duties are reliable, truitvorthy and not under the tafluence of any substance. legal or illegal, or mentally or physacally Lapaired from any cause, wnich I

• ta any way adversely affects their ability to safely and coerpstently perform their dutses. 3 1s Fitness-For-Duty Directive is intended to establish an environment which is free of drugs and alcohol and the effects of such substaases. In addition, an Employee Assistance Program is provsded to all esployees and is den igr.ed to achieve early intervention and provide for confidential assistance. Specimens collected will be used only for the purpose of satisfying the requirements of 1DCT1t Part 26.

II. SCOPE nis Directive applies to all Company personnel requiring unescorted access to protected areas, and also to personnel who

.an:- ha required to report to the T5C and EOF in accordance with enwrgency plans and procedures. This Directive does not apply to NMC employees, law asforcement personnel or offsite emergency fire and ,oedical response persommel while responding oasite.

!!. R_.E5pONSTIII!7T A. "he Vice Pres ident , Nuclear is responsible for,the overall implementation of this Directive.

g. The Mesager of Nuclear Musan Resources is responsible for the detailed impleemstation and adaimistration of this Directive.

identified as the Fitness For-Duty (ITD) Program Manager.

C. The Medical Review Officer is responsible for reviewing and examinias alternate medical explanettons for any positive test result.

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Nucinr Pow:r Division Administrctiva M:nual NPDAP 2.14 Revision 1 FITNESS-FOR-DUT( PROGRAM FOR Page 25 of 44 DUQUESNE LIGHT EMPLOYEES NCC'F.AR OROUP DIRECTIVE NO. 45 (continued)

C. Supervisors are responsible to assure all personnel under their supervision are fit-for-duty. In addition, supervisors are requared to snquire during call outs if the employee has abstained from the consumption of alcohol at least five (5) hours preceding the start of scheduled work. If the employee acknowledges consuspption of alcohol within the five (5) hours preceding the start of scheduled work, and refuses the call-out as s ignment, the employee will not be requsred to work.

If the employee does report sad is equal to or above the 0.06% BAC or deemed to be unfit for duty, the supe rvi.so r should send or have the employee taken home.

E. All personnel with unesco rt ed access or are assigned to duties under the Emergency Plan requiring access to the TSC and LOT are responsible to report to supervision any person on site reasonably suspected of being unfit for duty, or Lavolved in the use, possession or delivery of alcobal and/or drugs while on duty or e Company property.

F. All personnel are .rer:oired to report to the Medical Revtew Officer or his/her designated representative all medical treataent with controlled or behavioral altering substances.

G. All personnel are required to abstain from the use, sale or 8 possession of illegal drugs at all times and abstain free the k consumption of alcohol for a period of at least five (5) hours preceding the start of a scheduled work tour and during the period of any working tour.

H. The provider of the Employee As sist ance Program is responsible to inforis Duquesne Light Management (Medical Review Officer or his/her designee) when a deteruu. nation has been sade that any individua l 's condition constitutes a hazard to biaself/herself or others (including those who have self-referred).

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NPDAP 2.14 Nucle:r Pow:r Division Administr tive Manuit Revision 1 Paga 26 of 44 FITNESS-FOR-DUTY PROGRAM FOR DUQUESNE LIGHT EMPLOYEES I

WC'ZAR GROUP DIREC*IVE t#0. 65 (coattaued)

IV. REQUIRFJtDrrs A. Fitsess tor-Duty Supervisors are responsible for assuring that all personnel under their supervision are fit-for-duty and are capable of l performing their required work assigaseats. This Ancludes being cot under the effects of drugs (e.g. alcohci.

prescription. over-the-counter drugs and 111egal substances) and mental stress. fatigue and illness. When a supe rvisor suspects that an employee is not fit for duty (whose speech, physscal or sental behavior is considered to be aberrsat) he/she should take the following actions:

1. Xave at least one other supervtsor, if available,

, observe the employee's behavior.

2. Question the employee is as ettempt to determine the reason for his/her abnormal behavior. If a usien employee requests representation, the supervisor sha.;

coeply. (All observations and discussions should be decumented.)

3. Review the situation with his/her supervisors or other responsih1e departeest or group personnel to det ermine what course of actica is to be taken. The Fitness-For.

• haty Program Manager should be consulted in all cases.

6 If the employee's behavior indicates the possibility of drug abuse and/or alcobel comaussption. the employee is to be immediately escorted to the easite medical personnel. In their absence. they shouad

• be escorted to the Company Security Shift Supervisor for a breath analysis test and the Beaver County Medical Center for urinalysis .

5.  !! the earp loyee's behavior does not indicate the possibility of drug abuse and/or alcohol consumption and as deemed to be unfit for duty. the supervisor should sesd or have the employee takes home or if the probles verrants, taken for medical attention.

6. The Director of Security shall be notified to withdraw unescorted access.

7. Advise the employee that he/she is not to recort fer duty pending further investigation and that norshe will be contacted at a later date concerning when and -here to report.

-3 - ISSL'E 2 1/2/90 )

Nucbar Powar Division Administrative Manual NPDAP 2.14 }

Revision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 27 of 44 l l

/ DUQUESNE LIGHT EMPLOYEES j t .

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NUCII.AA GROUP DIRECTIVE No. 45 (continued)

8. Review with the employee that the Employe. Assistance Program is available for assistance to resolve a family or personal health probles that say be effecting his/her job performance.

NOTE:

Keep intervention la stad the four key elements of supervisory

a. Identification

b. Confreetation

c. Referral

d. Treatment B. Possesston or t*se Of Alcohol or Drums On The Job Vhen a supervisor observes the use or possession of alcohol or drugs by an esployee on the job or on Company property, he/she should take the following actions:

1. Contact Security for assistance.

(* confiscate the alcohol or drugs immediately.

supervision shall If possible.

assist and participate in this Cther function as well as in the following 1. investigation. I

2. Question the esployee concerning the incident as soon as possible. A Uplos representative shall be pressat tf requested by a Daica employee. (All observations and actsons should be documented.)

3. Review the situation with his/her superiors or other ~

re spons ible departeest personnel to determine i hat course of action is to be taken. The Tftness For-Duty Program Manager should be consulted in all cases.

(. . If' the esp 1,oyee was observed in the use or possession of drugs and/ist alcohol. he/she is to be tamediately l escorted to the easite medit.a1 personnel or, in their l

ebsence, the Company Security Shift Supervisor for a l breath analysis test and the Seever County Medical i l

Center for urinalysis.

S. '!he supervisor . his/her superiors or other responsible departmental personnel should inform the Fitness-For- ,

Duty program Manager of the details as soon as practical. If drugs are anvolved, then the Director of Security should also be notified.

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NPDAP 2.14 Nucle:r Powsr Division Administrative Manual ,

Revision 1 Pags 28 of 44 FITNESS-FOR-DUTY PROGRAM FOR , j Dt%UESNE LIGHT EMPLOYEES

.WCIZAR GROUP DIRECTIVE NO. 45 (continued)

6. If drugs are involved , request guidance from the f Director of Security conceressa additional searches. j modification of law enforcement personnel and '

dispositica of the itees confiscated.

7. he Director of Security shall withdraw usescorted access authorization within the Protected Area isusediate ly.

3. Prepare a detailed record of all facts and statements concerning the incident.

9. !avessiaations and searches of the property, employees and personal possessions, including lockers, tool choses and vehicles on Company property may be conducted for

, the purpose of detecting possessAoo of alcohol or controlled substances. no Coopemy will request Caton participasson when search tavolves Union personnel.

C. Possession or Use of Drums Of f '"he Job

1. De use er illegal sale or possession of narcotics, drugs or controlled substances, or the abuse of prescribed substances by an employee who is off duty and off Company property is unacceptable behavior, because it say af f ect on-the-job safety and perf ormance. Such use any result in disciplinary action up to and including discharge and tamediate withdrawal of usescotted access authorization.

2. All perseasel who are found to be Lavolved with illegal drugs off duty and off Coopeay property will be Lamediately removed from their job assignment and authorization for unescorted access will be withdrawn.

Rotentiam in the positica vill be coatingest on the employee success fully pass ing such t es t,Las as the Coupesy deese necessary and appropriate to verify cosciamed freedom from drug abuse durtag a reasonable probationary period. no Cospany may require participation in the Employee Assistance Program.

IssfK 2 l 1/2/90 l

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Nuclear Power Division Admini:trativa Manual NPDAP 2.14' Ravision 1 FITNESS-FOR-DUTY PROGRAM FOR Page 29 of 44 DUQUESNE LIGHT EMPLOYEES

{L NUCLEAA CROUP DIRECTIVE No. 45 (cosciaued)

V. DRt3 &ND OHOL *TSTING A. T! , following guidelines shall be used to detererne when an employee will be required to sukeit to drug and alcohol test.

1. Taitial &ccess Testi==

, All perseasel requiring usescorted access to the protected report to area, and persosoet required to physically the T5C and EOF are regaired t.e successfully complete chemical testias for involvement vtth drugs and/or alcohol before such access is taittally granced.

(See NOTE 1 below.)

NOTE 1: Any test, candected la accordance with 10CFR26 that was

' done withis siaty (60) days of Laitial access, could be used for granting usescorted access.

2. Randos Testina Umaamounced tests will be conducted is a randes amaner.

The test will be administered so that a person r

completing a test is immediately eligible for another

= = == -a d test. Raaden testing will he conducted as a

{ rate equal to at least 100% of the work force per year.

t' 3.

Reasonable cause Testima - (See NOTE 2)

Testing for cause will be demo for reasons listed below; however, they are met all inclusive. The Company may test for any illegal drugs darias a "for cause test". or analysis of any specimes suspected of belag adulterated or diluted through hydration or other seams.

a. As soon as possible followims any observed behavtor indicating possible substance abuse.

b. After accidente involving a failure in individual perfomesco resulting ta personal injury,

c. In a radiation esposure or release of radioactivity in excess of regulatory limits.  !

I

d. Actual or potential substaattal degradation of the level of safety of the plant af there is reasonable suspicico that the workers behavior contrabused to

• che event.

e. After receiving credible info rmat ion that as tndividual is abusing drugs or alcohol. * ,

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1 MJCII.AA GROUP DIECTIVE No. 65 (continued)

f. Tavolvement in the use, possession or delivery of a controlled substance or sicohol while on duty or on Cospany property.

g. Involvement in the use or delivery of a drug other than a controlled substance while on duty or on Coerpany property without authenticated sedLcal evidence.

h. If alcohol has been consumed within five (3) hours of a required reporttag tour of duty resulting from a call-out, only a test for alcohol wt11 he administered.

NOTE 2: Every espicyee who is ree-aded for a chemical test due to reasonable cause by the empicyee's supervisor will be reviewed by the Fitness-For-Duty Prograa fianager and a detersiastion will be made of the appropriateness of such a tast before the employee is notified of the testing requirement.

4. Follow-Cp Testins

a. On sa unannounced basis, personnel who have completed rehabilitative treatment for drug and/or alcohol vill be required to submit to cheetcal testing to verify constnued abstinence free the use of drugs and/or alcohol (ezcept for self-referral).

b. On an unsamounced bas is , all personnel who have tasted positive at another nuclear power plant in accordance with a Titness-For Duty Directive that resulted in on-duty Lepaireest subject to a plan for treating s ubs tance abuse (axcept for self-referral treateest), or removed free activities or denied unescorted access , as determined by suitable inquiry.

c. Any person granted unescorted eccess or whose access is reinstated under a. and b. above. for drug-related treatment must be given u.nannounced follow-up tests at least once a ooeth for four G) sonths and at least once every three (3) sonths for the next two (2) years and eight (8) sooths after unescorted access is reinstated.

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d. Any person greated unescorted access or whose access is retastated under a. and b. above for alcohol-related treatment, must be - gives unsanounced follow-up tests at least once a month for four (4) months and at least three (3) times to the samt one (1) year and eight (8) eenths after uuescorted access is reinstated.

3

5. Unscheduled Work'1am Tour 1 j

i Employees who have accepted an unscheduled working tour (call-out) and have acknowledged consumption of alcohol within the five (5) hours prior to the start of the scheduled working tour, util be required to submit o a breach analysis . If the results of the breath analysis is below 0.04% BAC, the supervisor shall make a determination as to whether the employee is fit to perform the task assigmod. If the results are equal to or in excess of 0.04% BAC, the employee will not be assigned to work and the supervisor should send or have the employee takaa home.

VI. REMARILITAyIOK/ DISCIPLINARY ACTIONS A.

lI' k

Determination of the presence of a drug (confirmed Positive Test Results) resulting free chemical testing shall require the fellowing actiosa:

1. Regular and temporary employees whose presence of a drug (confirmed Positive Test Results) without authenticated medical evidence, as detsruined by the Medical Review of ficer, will result ta the employee being relieved f rom duty, placed ca tadefialte suspenstom and unescorted access densed for a minisuss period of fourteen (14) days and subject to rehabilitation procedores which may include a residence program.

2. Any subsequent caafirmed positive test must result ta removal free unescorted access to protected areas for a nimisias of three (3) years from the date of removal and placed on indefinite suspension pending review.

3. Any confirmed Positive Test Result through the follow-up testing process or any other determinat too of subsequent involvement la the sale, use or possession of 111ess!

substances will result ta permanent denial of unescorted access, and the employee placed on indefiatte suspension -

j pending review. '

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. . .4- .If ..the . presence of a drug (confirmed Positive Test) is the result of verified medseal treateemt. the employee permitted to ' perfore ' his/her normal job will be functions unless specifically prohibited from doing so by the Medical geview Of ficer. .

4

5. Employees who are directed to sukeit to a urtaalysis la accordance with this Directive and refuse, will be subject to removal for cause. The employee vall be placed om indeftaite suspensten and denied unescorted access pending review.

6. Employees who are required to subeit to urinalysis for reasonable cause, shall be placed on a paid ." e ave of sheence pending the outcome of the analysts. If the analysis is negative, no record of the leave will be kept. If. the analysis is coefirmed pos&tive, rehabilitative er, if warranted, disciplinary action will be initiated in accordance with this Directive.

The employee will be placed os indefinite suspension pending review.

3. Determination of a blood alcohol content to be equal to or in excess of 0.04% by as laten 11yser shall require the following actions:

1. The presence of alcohol, equal to or in excess of 0.04%

of the blood alcohol content, will be cause to relieve the employee frus duty, deny unescorted access, place on indafinite suspeasion and possibly aubjeet to init1aeton of rehabilitates procedures lacluding a residence program with the exception of reporting for an unscheduled working tour (call out).

2. Amy subsequest occurresse of being tested equal to or tn excess of 0.04% of the blood alcohol sootent, the employee will be relieved free duty, denied usescorted access, placed on indefinite suspeas tos poeding review and may be subj ect to initiation of rehabilitation procedures which may include a ressdence program, with the exception of reporting for an unscheduled working tour (call out).

3. Employees who are required to submit to an incozilyzer test ta accordance with this Directive and refuse will be subject to removal for cause._ The employee will oo

• placed as indefinite suspension and dealed .ac.e s co r t ed access pending revtew.

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4 Employees who are required to otheit to as incontirser s test for reaseeable cause and request a blood alcohol test for additional confirmation. shall be placed.on an unpaid leave of absence pendias the outcase of the analysis. If the analysis is positive (equal to or in excess of 0.061 bleed - - alcobel concentration) rehabilitation and/or disciplinary action will be laitiated La acteedense with this Directive.

3. An employee who reports for an unscheduled worklag tour.

La accordance with secties V.3 of this Directive and the results of the breath analysis are equal to or in excess of 0.04% Bec on three (J) er more occasions in a current twelve-eosch period or five (5) or more occessoas sa a current 36-month period, will be counselled by the

.4edical Review Officer.

C. Any sadividual determiaed to have been involved in the sale, use or possessten of illegal drugs while within the protected area of any suelear power plant will be dealed unescorted access for a minimus period of five (5) years and placed on sadefinite suspensies pending review.

D. Any individea3 detesuimed to have been tavelved in the sale, use or possession of alcohol uk11e withis the protected areas of any nuclear power plaat will be denied uneseerted access, placed on indefiatte suspension pendlag review.

E. Any fadividual who has been dealed access for three (3) years or more for the illegal sale, use or peasession of drugs and who may be regnesting unescorted access at Beaver Valley Power Station will only be greated usescorted access upon receiving satisf actory medical assurance that the fadividual has abstained fres drugs for at leas t three (3) years.

Grasting of usescorted access wall be contingent upon satisfactory eamagement and medical assurance of the individual's fitness to adequately perfore his/her job duties, VII. Ap?EA13 An appeal process will be afforded to all employees in the following saamers A. Upon request of the individual or Union, the split sample *,

will be seat for analysis is accordance with the 1eplementation Procedure.

3. *

.!anagement employees can utilize the Open Door Policy.

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NUC11AA GROUP DIRECEVT. NO. 3' (cestiansed4 O I ... J ' '

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C. Union employees can utiliza che grievance procedure as , .

s described. is the Laberl Agreement, under, artiste 11.;

hy individual who is the embject of a drug or alcohol test shall,

~

upon writtee roguest, have ase==s to any records relating to his or her tests and any records. relating to the results of any relevant laboratory - sortificet tes. review, er revocation of ce,ccifIcat1on proceedings.

VI*I. covrYNUANCE Pilov!SION In the future. legis lative, readlatory and/or judicial action by governeestal authority may conflict and tavelidata spectfic provisions of this Directive. Is. that event, the ressaader of the Directive and all previsions not specifically invalidated by such legislation will reesis is effect. In the eveat technological advancee in the aa417 sis present opportunities . to Leprove reliability of results or improve the comfort level of employees required to subsit specimens for analysis, this Directive will be altered accordingly after full consuaication and advertislag of the changes with the Union and employees.

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Nuclear Pow:r Division Administrttiva Manual . . NPDAP 2.14 Revision 1 FITNESS-FOR-DUTY PROGRAM FOR .

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.WCIIAR GROUP JIAECTIVE NO. 65 (cestimmed) u. I

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. Tf? NESS FOR DUTT PROGRAM TMPEZ?tDerATION PRa - '

t> ' e'j s.

Drug and alcohol testing can technologically be administered using multiple analys ts methods; however, is orde r to clarify ^the procedure for any analysis of method required selected actions for implementation, the following specific aussnary is preeimated.

1. CRINE. 3!40D AND IN70KILYZER A m v315 Uriae and tatoxilyser analysis is a requirement for all personnel requiring unescarted access to precocted area. T3C and E0y la accordance with energency plans and procedure. To assure strict confidentiality and the utmost control of this procedure, the following guidelines will be used in the collection and transfer of the uriae and blood (if applicable) to the laboratory.

4.

Appropriate procedure will be established by the Medical Staff in order to assure that the asaminee providae en authentic urias sample and accurate breath analysis.

B. Applicants will be required to provide positive identification and to read and sism a Cassent-To-Testing form (copy of which is attached). Refusal to sign the form will

(, require the drug screen / breath analysis procedure to be terminated and the Ladividsal will be handled la accordance with the Nuclear Creep Directive No. 45 (Titnesc-For-Duty) or Nuclear Group Directive 29 as applicable.

C.

The exaoimee will be required to remove all outer garmenta (Jacket, coat, sweater), and will not be permitted to carry a purse, brief case or any type of carry bag into the collection roce. If the examines is waaring long sleeves.

these should be rolled up and the anastaee should be visually eaamined to ensure the examtaee cannot access a container previously filled with a foreias substancethe a prepared sample. The room used to take the specimen should not have runalas water. If a rose without runnlag water is not available, the water supply valve to the sink should be shut off and the fauceta at the s tak should be opened. Any totlet should have coloring added to both the bowl and tank. This is does so the urtae sample cannot be diluted. The naaminee should met be permitted to drink any liquida until a sample is produced. The individual shall be instructed to wash and dry his/her hands prior to urination.

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• iLCII.AA udOUP DIRECTIVE too. 45 (continued) <

r MP!J232ffATION pBOCEDUR$ (contianned)- MHMeWn WJ . - '

D. Refmaal of'as amanisse to provide e istine specimes' or treath emelysis' wLil require the Company to deny er withdraw unesserted access. The Medical section er designee sha11 refer such a reimaal to the examamee's as s igned . Unit or superviser and will' notify the Director of Security for

. appropriate acties.

E. The followis,s esterials are required:

1. Special " Chain of Custody Request

• forms (3 part)

- 2. W o sealed sterile containers for urine

3. Sterile vacuum tubes and needle assemblies for blood

4. ho special 5" a s" Chain-of-Custody bags (n ese bass have the chata of custody procedure praated in RED on the outside). One bag for blood

5. Evidence tape

6. ho intomilysers I. L1 TINE Col.IEITg A. One sterile container will be gives to the emasines.

B. Direct obse rvaties of the callectico process will not be required maless the medical perseasel is charge of the collecties suspect the esamisee is attempting to adulterate or substitute the sample. The Medical perseasel will monitor the collection process is order to estatain control of the integrity of the specinea. The eaantase will be requested to urinate directly . Ante the container. The contaamer wt11 be filled for a maaisus collection of 60 m1.

F C. Upee exitias the cellectima room,'the emasiaee wall suosit the specimes container to the Medical perseasel who an the presence of the esamisee will lattiste a temperature test and/or a specific gravity test. If the test results verify the specissess are autheatic, them the specimes as the cantainer will be divided isto two smaller s amples for shipment and/or storage. The examisse will them be requested to imat tal the evidence tapes and sign the pe rsament record book certify $ag that the spectoons collected are s.a fact the

• spectness provsded by his or her. The contassers will then be sealed with the evidence tape La the presence of the examsmee. Vbenever there is reason to believe that a particular individual may alter or substitute the artne specians to be provided, a second specimen shall be obtsaned 155tJE :

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I FITNESS-FOR-DUTY PROGRAM FOR l jy, DUQUESNE LIGHT EMPLOYEES s-fgg ./

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NUCI. eda GROUP DIRECTIVE NO. 45 tcesataued3 - . ' '

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IMP 1DtENTAT'ON PROCEDURE (coatinued)'

as seen ~as pesstble under the direct"observattom .::h ' y %A W .

, ~

of a same gender collection site person. Vhere appropetete, esasure .

will be taken to provost additieaal aydrattoa. _

D.

The Medical perseasel. or designes, wi11' complete the " Chain of Custody Request" fors which tacludes the t:me. date, and sisaature for each specimes container. > -

E. The specimes and the original ecpy of the foris are placed in the Chaia-of-Custody bag and sealed with evidence tape. Dae

, copy of the form is kept by the Medical Section, and the reestains copy is attached to the outside . of the sealed Chaim-of-Cuatody bag.

. T. The %edical Section vall rotata one specinea container at tts f acility and estatain the specimen in proper env a ronmental conditions. This specimen will be rotasand and used as a second specimes for analysts if the first specimes is positive and the exasiaes or Unica requests a second analysis. his request must be made withis three (3) days of

• notification of a posittve result. The cost of the second analysts will be borne by the requestor (eassinee or Union)

( and arrangeoests for the acceptable payment must be made at the time of the request. The split sample will be forwarded on the day of the request to another 1815 certified laboratory that did not test the aliquot saarple . The purpose of the l

second analysis will be to provide the esaminee r.8 the Unira evidence of the accuracy of the first analysts. If ase tattial confirmed positive test analysis is not reconta. ed by the second analysis, the overall test procedure will be considered as a negative result and the esaminee or Caton wt11 he refunded the cost of the second easiysis.

G.

The Medical Section shall call the courser service for same day uriae specimes pickup for one of the containers.

H. Those persons headling the sealed spcimes will use the requisition form attached to the outside of the Chata-of-Custody beg as em acknowledgeoemt form for chats of custody.

I. The Chain of-Custody bag is not to be opened ur.til at is received by the designated personae 1 at the testtng laboratory who will documeat the tstegrity of the seal and place the specimes in locked storage until processtas. ,

J. "he Medical Section will normal ly receive the urtae drug

, screen results vathan eventy-four l24) hours if the results are eegative. It may take two (2) days 'to recetve confirmation of pacitive test r e su l e.s . These sames util vary dependent upon the specific, *.as, oratory serytce used for such .

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scr=== tag.. .The laboratory...will farmisk documentation someting the credibility of< the stain of sessedy as well as the results of the specimen analysis. It'is- imperative that confidentiality is asistained when the -Fitness-For-Duty Program is utilised. 411m reseres ,results <and opimians resultsag free such tests wi,11,be kept confidential.

! K. The results of the drug screes test will. become a part of the i

! saassaae's medical records and/or anclear access records, and will be reviewed on a limited, casfidential basis with only those Company officials .iavelved la ensinistration of physical eneminatAons, drug screens, usescorted access , or disciplinary matters. When the Medical Review Officer. After final review of results, deteresans a positive test analysis, he/she shall inform the Titaess-For Duty Program nasager, or his/her desigasted representative who will be respoestble for instituslag a review of the =individsal's employeest status and/or unescorted access status. Medical perseasel will also inform the Director of security.

!*I. INTQXII.YZER AND 1!40D COI.IIC"fTON

a. Alcohel breath tests shall be delayed at least fifteen (15) sinutes if any searce of south alcohol (e.g.,

breath freshesers) or any other substances are inges ted (e.g.

eettag, seeking, regurgitation of scesack .centents free .

vaalting er burping). The cellecties site persea shall l

ensure that each breath specimes takes cases from the end, rather them the begianias of the breath empiraties. For each screasias test, two breath specimens shall be cellected from each individual as less than two simetes apart and no more them tes (10) maastes apart. The test results shall be considered accurate if the result of each esasurement is withis plus er aimme tem percast (2107.) of the average of two seesurements. If the two tests 'de met agree, the breath testa shall be repeated on asether evidentie,1-grade breath analyn'is devise. Confirsetery testing is accomplished by repeating the above precedere on another evidential grade breath analysis 4evice.

B. If the slcmbol iveath screen test indicates that the indiviemal is positate for a BAC at er above the 0.0(. percent cateff level, a confiscatory test for alcohol shall be done with emether breath sessure Lastrument. Should a person demand farther confirmation, the test must be a gas chromatography analysis of blood. All vacuum tube and needle ,

assemblies used for blood collectima shall be factory-s te rilised. The collection site perses shall ensure that they remain properly sealed until used. Antiseptic swabbing of the skia shall be performed with a nonetbanol antiseptic.

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NUCI. EAR GROL*P D1hECTIVE No." 45 (continued) '

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4

!"plEMENT& TION P*** NJ"E,(costimmed); ,

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5terile proceshares shall be followed whee drawing bleed andi  ;

tressferrias the blood to a storage coetainer; : im addittoa. l' the contaiser east be sterile and sealed.

~

C. Upea request of the esamisee to have confirmatory blood test, the medical persensel

• will draw a vacuum tube of ' blood free the esamisee. '

O. In the precease of the emasiaee, the vacuum tube will be stated with evidence tape and the eneminee util be required to initial the evidence tape.

E. The Medical persommel. or designee, will complete the " Chain of Custody Request ** form which includes the time, date, and signature for each semple coat, aimer.

T, The sample and the' original copy of the fers are placed in the Chain-of-Custody bag and sealed with the evidence tape.

One copy of the form is kept by the nodical $sction, and the remainias copy is attached to the outs ide of the sealed Chaia-of-Custody bag.

G. Medical Secties perseasel or designated representative (NOTI

1) shall call the seerior service for same day blood sample

( H.

pickup of the container.

These persons headling the sealed sample will use the requisition form attacked to the outside of the Chain-of-Custody bag as en askasvledgemeest foca for chain of custody.

NOTE 1: If the Medical perseasel cellecting the blood specimen are not Coupeay medical personnel as detailed i.n Section III.L of this procedure. then the Duquesne Light Company l supervisor la charge will motify the medical authority that the "- ; a Medical Section will motify them as soon as possible but no later then the seat work day as to how the specimes will be transported to a laboratory for smalysis. The Medical section may at their discrettee select the hospasal facilities to conduct the ce llectim'n'. 1

1.  ;%e Chain-o f-Cus tody bag is not to be opened until at is received by the des ignated personnel at the testtna laboratory who will document the integrity of the seal and security of the sample until processing. It is imperattve that confidentiality be estatataed when the Fitness-For Duty Program is utilised. All- records. results and optatons '

resulting free such tests will be kept confidential.

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NUCLEAR GROUP DIE CTIVE NO. 45 (continued)

IMPIIMDrTATION PROCEDURE (c'estinued[

- m . ..r .,

J. The results of the blood ' analysis will become 's part of the emaaimee's medical records and/or nuclear access records, and will be reviewed os a lisated, confidential basis with only those Company officials involved ia administration of j

paystcal examinattees.' drus/ alcohol screens, uneocorted '

access setters, or disciplinary easters. When the Medical

• Review Officar, after final review of results, determines a positive test ammlysis, he/she shall inform the Fitness-For-Duty Program Manager or his/her designated representative, who will be responsible for institustas a revtew of the sadividual's employment status and/or unescorted access status. Medical personnel will also inform the Director of security.

K. If the Chasa of Custody is vioisted the test results will de considered void and a review with the initiattag party will be conducted by the Medical Section to determine if another sample should be obtained.

L. la the event the implementation procedure noted above is not performed by Medical Staff, all designated testing functions will apply to the medical representative designated by the Company.

M. Hospital and/or other medical facility listed below shall be deatsmated as the locaties where the blood / alcohol collection may be perfereed as as siternative to the Medical Section when they are usava11able. When this location is selected by the esamisee's supervisor as the location for the collection.

the supervisor will accompany the examinee to the facility, and present the sedical authority at the fac.111ty with the medical equipment and imatructions to implement the collection procedure and the Chats of Custody. The facility listed below has had a Purchese Order established with the Company to authorize paymeat for collecgica they will perform.

Medical yacility: Beaver County Medical Center Address: 100 Dutch Ridge Road Beaver. Pennsylvania N. If the Chain of Custody La violated, the tes t results will be considered void and a review with the tattiating party will be conducted by the Medical Section to deterasse if another

• spectmen should be ottataed.

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Nuclear Power Dmson Administration Manual . i , , , # NPDAP 2.14 :

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.WCf2AR GR@ Os2EC" VE'NOUS (ccat1muod

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!V. .

• ntINE. 3t400 AND INTUXILYTER SCREEN!HG ':tSTIMC PARMRs A. Initial scteenlag 'of' uriae and blood specimaas shall be esaducted by a Departomat of Health & Muses Services certified laboratory procedure for all specimens which utilizes a chata of custody submitted Company. ' for maalys is by the

3. *sitial urtae screen 6as immunoassay method.

wall be conducted by ussag C. Initial breath analysis will , be condected by us ing a evidential to the grade breath alcohol analysis devtco that conforme

• National Highway Traffic Safety Adminis t ra tion Standards (49Cn64453) and any applicable state statutes.

3.

The f ollowin g initial cut-off levels shall be used when screensas speca.sens to determine whether they are positive for the indscated substances.

Initial Screen Positive Thresholds Values

( h Marijuana Metabolites. . . . . .... 100 Cocaine Metabolites.

Nancarems /*!il li lit er

. . . . . . . . 300 Opiatas. . .

300

• Phencyclidine. . . . . .

. . 25 Aarphet amines . . . . . . . . .1000 AlcohoI. . . . . . . . .. . . . 0.06% BAC

'23 ng/e1 is Lamunoassay specific for free sorphine

- la = 155LT. 2 1/2/90

Nuclear Power Division Administrative Manual, ' ,/

_ m.pme c.,cw - ' ~J~.NPDAP Revision 1 2.14 .  !

• ,- m.m.-

• zs w -d  !

FITNESS-FOR-DUTY PROGRAM FOR -

1 DUQUESNE t.lGHT EMPLOYEES % * ##%d[K U #. ' '$ 7 % ;"^ [ '

s )

W4 r

., A%;fn psy: - ;; f +

. :. ;u e , . ,.y NUL.A. EAR GROUP DIRECTIVE,.N,O. N '7

, g 45 (eastnamed)-- n +,

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Mt a s, .s w 4 - o v.3; <

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v. URIwt. afAOD AND INT 0XILYZER CQPTIRMATCFT TTITING PARA.6 j A. Positive Ladication , ser -aay of ;' the . ; drugs identified da Paragraph IV.D will require a confirmatory test for each drug identsfied as peettive by the'isitial screen.

B. A confLamstory test procedure for uriae and bleet, -if .

applicable, will require. the use of the Gas I Chreestography/ Mass spectrometry method (GC/MS).

C. A confirmatory test precedure for breath analysis will be accglimbed by repeating the procedure s.a Paragraph III.A of this procedure, so another evidential

• grade breath analys is device. ,

I D. Confirmaties test analysis' shall b "'a onducted for the j followtag drugs, as warraated by the laitial screestag '

analysis, ussag the following threshold values as a pos&tive f indication. '

Confirection Positive Thresholds values h Nanoarees/ Milli! ster Marijuana Metabelite. .... . . . . 15 * '

CocaAme Net 6 'ite. . ... . . . . 15 0 -

Opiate Morphine. . . . . .. . . . 300 Codeine . . .. . . ... . . .. . 300 Phencyclidiao . . . . ... . .... 25 ,,

Aephetastaes Amphetamine . . . . ....... . 500 Motheephetamine . . ..... . 500 Alcohot . . . . . . .... ... 0.04% RAC ,

• Delta-9-Tetrahydrocammabimo19-Carborylic acid

• • lenzoylecgonine e

., ~ g9

!$5UE 2' 1/2/90

. )

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' NucleIr Power Division Admimstratrve Mamsal NPDAP 2.14

, ,. ,~ .

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• M- Revision 1 -

FITNESS-FOR-DUTY PROGRAM FOR c _ wry 1 5 ,, Page 43 of 44 :

1

. DUQUESNE LIGHT EMPLOYEES ' - # "nMSW ^ '*##

1 . + . . .

i I

l s.

quig ja Yn - '

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• NUC ZAR GROUP DIR1CTIVE .,':

, - , . -NO. 45 (contiansed)-..

. . m rw m -

!"P'.J.F.I?(T& TION p*""*{

(cestiamed) w 7.,

l CONSENT TO TESTING FORN l A ,. , o I,

subett , do hereby knowingly agree to to a breata analysts and to provide a blood and/or urtae specimen to Duquesne Light Company and its de'signated spectees collection agency and/or laboratory catect theand to persit them to analyse er blood and/or urine spectmen to l presence of drugs and/or alcohol. I give ey permasston to the destgaated specisea collectLoa agency and/or laboratory to release the results of the blood and/or urine analysis to Duquesne Light Company.

• ist G the proscription medication and over-the-counter preparettons

, you have taken within the past thirty (30) days. _

F.

l

\

Exastate is required to sign the Consent to Testing form in accordance utth 1CCTR26 Appendia A, 2.4(g)(4) .

51snature Date F0R C0MP&NY USE ONLY <*

'OCTR26 Appendtz A, 2.6(J) "Tailure to Cooperate". If an individual refuses

!=

ccoperate wath the urine collectico or breath analysis process (e.g.,

refstal to provide a campiece specimes, complete paperwork, taittal s cet taen ) , them the Medical Review Officer shall report the failure to ooperate to the appropriate management.

l Reason:

Date; tse:

"allectier. Site Person:

l sagnatura l

l

(

ISSUE 2 1/2/90 f

L_____________..___._----_...-.-_

y . .

FITNESS-FOR DUTY PROG %M FOR me.: n ,._ l > , . ' Page 44 of 44 ..

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NUCIIAA CROUP DIRECTIVE NO. 45 (continued)

< ~ +--st 'h r Quality Assurance Review:

Y2_!N'~ '- Y //b//d1 .

Approval:

$4 h.L/ to-n- 91 Data fice Pres, dent - Nuclear App roval:

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ISSUE 2 1/2/90 i

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Unit 1 10M-07.5 Beaver Valley Power Station Issue 2 Revision 7 Chemical and Volume Control System Page 1 of 1 l

5 Figures and Tables FIGURES AND TABLES

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~ - - 700 600 -

11500 -

500 3600 -

- 1400 3000 -

l

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- 1000 .

- 30 150 -- - 20 500 15

(

100

- 10 10 f

BORON ADDITION - REFER TO TABLE 1 FOR CORRECTION FA FIGURE 7-7 k

I

iOM-07.5 Beaver Valley Power Station Unit 1 issue 2 Revision 7 Chemical and Volume Control System Page 1 of 1

!I Figures and Tables FIGURES AND TABLES

(.

l t

,__ 10 - 60 l

'.. 100 500 - --

55

- 50 400 - - - 45

_ 90

- 40 300 - - 35

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Unit 1 10M-7.5.8.1 Beaver Valley Power Station issue 4 Revision 0 Chemice and Volume Control System Page 1 of 1 l f Figures and Tables TABLE 7-1 NOMOGRAPH CORRECTION FACTORS

(

PLANT CONDITIONS CORRECTION FACTOR T(AVG) PRESSURIZER LEVEL (K)(See Note)

PRESSURE (PS;G) ( F)

Normal Operating 1.00 2235 547-570 1.05 1600 500 No-Load 1.10 ,

1200 450 No-Load f

1.16 800 400 No-Load 1.18 400 350 No-Load 1.20 400 300 No-Load 1.35 400 300 Solid Water 1.28 400 200 No-Load 1.40 400 200 Solid Water 1.47 400 100 Solid Water

(.

Note: CORRECTION FACTORS ARE APPLIED AS FOLLOWS:

a. Boron Addition and Dilution Total Volume Nomographs V(Corrected) ==

K x V(Nomograph)

b. Boron Addition and Dilution Rate Nomographs d (Nomograph)  ;

-f (Corrected) == f x d 0

l I

s

Record Type #A9.3308 i

DUQUESNE LIGHT COMPANY Beaver Valley Power Station l

Unit 1 i

10M-19.4.E(ISS3)

DECAY TANK DISCHARGE issue 3 Revision 2 -

Prepared by Date Pagesissued Effective Date l L. R. Montanari 07/30/96 E1 thru E6 AUG 0 61996 Reviewed by Date Vahdated by Date J.P.Keegan 07/30/96 N/A OSC Meeting No. Date Appr by, ate OMCN 1-96-159 d f[ l CONTROLLED

- - _ - - - - - - - - - - - - - --- - - - - BVP8 UNIT 1

Bravar Vellay Power Ststion Unit 1 10M-19.4.E(ISS3)

Gaseous Waste Disposal System Issue 3 Revision 2 l Operating Procedures Page E 1 of 6 k DECAY TANK DISCHARGE PURPOSE To provide instructions to discharge the contents of a gaseous waste decay tank to the atmosphere. Instructions are provided for discharging [1GW-TK-1 A] Decay Tank with mark numbers in parenthesis for [1GW-TK-1B,1C] Decay Tanks.

PRECAUTIONS -

1. Do not discharge more than one decay tank at one time.

2. Do not discharge a decay tank until Chemistry notification is complete.

INITIAL CONDITIONS

1. The meteorological instrumentation specified in Technical Specification 3.3.3.4,

" Meteorological Instrumentation", are Operable.

2. [FR-1GW-108] GW Flow to Cooling Tower, indicates less than 1400 SCFM.

3. The applicable radioactive gaseous effluent monitoring instrumentation channels specified in ODCM Appendix C 3.3.3.10. " Radioactive Gaseous Effluent instrumentation", are Operable or the applicable Action Statement has been met.

. Note: The Rad Tech must enter the Control Room to adjust the alarm setpoints on the analog instrument. The Rad Tech performs the adjustments required by the RWDA-G and initials it.

4 Radeon has been contacted so that the HI and Hi HI Alarm Setpoints can be adjusted in accordance with the Health Physics Manual, Chapter 3, Procedure 6.6, 6.6A. .

Note: The NSS/ANSS at Unit 1 and the NSS/ANSS at Unit 2 signatures denotes approval for l discharge, that only one batch RWDA-G is being discharged at one time and that the i appropriate alarms have been adjusted.

l S. The NSS/ANSS at Unit 1 and the NSS/ANSS at Unit 2 have reviewed the RWDA-G, signed and dated the RWDA-G, signed and dated the RWDA-G at the PRE (discharge l l authorization block).

l l Note: Notifying Chemistry will enable the Chemist to obtain the appropriate tritium sample.

The Chemist will sign and date the RWDA-G at PRE (discharge authorization block) for verification of this notification.

6. The ANSS or the Operator has notified the Chemist of the intent to discharge the decay tank.

7. [1GW-276] Unit 2 Isolation to GW Decay Tanks Discharge Header is closed.

Baavar Vallny Powsr Stttion Unit 1 10M-19.4.E(ISS3)

Gaseous Waste Disposal System issue 3 Revision 2 i Operating Procedures Page E 2 of 6 i DECAY TANK DISCHARGE l 8. [TV-1GW-103A1 (10381) (103C1)] 1 A (18) (1C) GW Decay Tk Feed Valve for the decay tank to be discharged is closed. j l

9. [1GW-F-1 A (1B)] GW Disposal Blower is operating.

INSTRUCTIONS CAUTION: ONLY ONE [TV-1GW-101 A (1018) (101C)] 1 A (18) (1C) GW DECAY TK SAMPLE RETURN OR N2 FLUSH VALVE SHALL BE OPEN WHEN A GW DECAY TANK DISCHARGE IS IN PROGRESS TO PREVENT AN INADVERTENT DISCHARGE OF MORE THAN ONE DECAY TANK.

1. When Radcon is ready to sample, open [TV-1GW-101 A (101B) (101C)] 1 A (1B) (1C)'

GW Decay Tk Sample Return or N2 Flush.

2. When Radeon reports that sampling is completed, close [TV-1GW 101 A (1018)

(101C)] 1 A (18) (1C) GW Decay Tk Sample Return or N2 Flush.

a. Independently Verify that [TV-1GW-101 A(1018)(101C)],1 A(18)(1C) GW Dewy Tk Sample Return or N2 Flush, are Closed AND Document in 10M-54.2 S1-4 0),

f Nuclear Control Operators Report.

r,.

Note: Discharging a decay tank during stability, classes E and F should be avoided. It is preferable to discharge a decay tank during stability classes A through D.

3. Check [RIS-1GW-108A (1088)] Gaseous Waste Particulate and Gas Monitors HI and

< HI HI setpoints agree with the setpoint in the Radiation Monitor Setpoint Log.  !

l 4. Perform a Channel Check and a source check on [RM-1GW-108A (1088)] Gaseous i

Waste Particulate and Gas Monitor and record in the NCO Report.

5. If ARERAS is operational, then obtain the current meteorological data in accordance with 10M-581.4.N, " Obtaining / interpreting Meteorological Data Displays".

a. Make a hard copy of the data using the video copier located next to ARERAS, using 10M 581.4.D, "Use of the Tektronic 4112/4113 Terminals".

b. Attach the hard copy to the RWDA-G.

c. Mark the RWDA-G Authorization Number on the hard copy at the start of the l

discharge.

6. Mark the date, time RWDA-G Authorization Number, and the Operator's initials on the following recorders at the beginning of each discharge:

a. [FR-1GW-105] Decay Tank Bleed Flow Recorder,

b. [PR-1GW-103] Decay Tank Pressure Recorder.

c. [1RR-200] Radiation Monitor Level Recorder.

l 1

Bssvsr Valley Power Station Unit 1 10M-19.4.E(ISS3)

Gaseous Wasta Disposal System Issue 3 Revision 2 Operating Procedures Page E 3 of 6 DECAY TANK DISCHARGE

, Note: An approved RWDA-G is effective for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after sample time. If a discharge is

{ not initiated within this period, a confirmatory sample shall be analyzed to extend l the effective period of the authorization.

7. Record the date, time, decay tank pressure in PSIG and OPER INIT (initials of the operator making these entries) on the RWDA-G at the beginning of each discharge.

I

8. Check closed [FCV-1GW-105] Decay Tank Bleed Control Valve by checking l [AM-1GW-105] in MAN with output at 0%.

9. Open [TV-1GW-103] GW Decay Tank Disch to CTWR Viv.

CAUTION: ONLY ONE [TV-1GW-101 A (101B) (101C)] 1 A (1B) (1C) GW DECAY TK SAMPLE RETURN OR N2 FLUSH VALVE SHALL BE OPEN WHEN A GW DECAY TANK DISCHARGE IS IN PROGRESS TO PREVENT AN INADVERTENT DISCHARGE OF MORE THAN ONE DECAY TANK.

10. Check closed [TV-1GW-101 A (1018) (101C)] 1 A (18) (1C) GW Decay Tk Sample Return or N2 Flush, for the decay tank to be discharged.

i 11. Check closed [TV-1GW-110A (1108) (110C)] 1 A (1B) (1C) GW Decay Tk Sample Viv, i i for the tank to be discharged.

Note: At the end of each month, the operator shall make an entry for discharge stop and start, i.e., March 31 at 2400 hrs discharge stop and April 1 at 0001 hrs. discharge j start, in order to norma 4ze computer data for what was discharged each month.

l

12. Open [TV-1GW-103A2 (103B2) (103C2)] 1 A (1B) (1C) GW Decay Tk Bleed Va*lve for i the decay tank to be discharged as follows:

l a. Place its FILL-OFF-BLEED selector switch to the BLEED position.

b. Push and hold [TV-1GW 103A2 (103B2) (103C2)] Valve Open Actuation RESET l

l pushbutton until [TV-1GW-103A2 (103B2) (103C2)] fully opens.

l l Note: In conducting his review, the NSS/ANSS shall consider the correct source selection, radiation monitor setpoints, radiation monitor setpoint checks, dilution flow, RWDA-G in e e, p icedure in use, boundary valve alignment, Chemistry notification, Radeon nc/a .cy, ..i, intended discharge rate and proper documentation to the current step.

~

13. Prior to INITIATION or RE-INITIATION of all radioactive waste discharges, request that the NSS/ANSS review the steps and alignments conducted to this point and authorize the INITIATION or RE-INITIATION of discharge.+

14. Record an entry in the Nuclear Control Operators Report (S1-4,5 or 6) stating the I

NSS/ANSS has authorized the INITIATION or RE-INITIATION of discharge and RWDA-G number.*

\

Beevar Valley Power Station Unit 1 10M-19.4.E(ISS3)

Gaseous Waste Disposal System issue 3 Revision 2 l

Operating Procedures Page E 4 of 6 i :

l( DECAY TANK DISCHARGE

\

1 1

15. Notify the Chemist that the gaseous waste discharge is starting.

16. Slowly open [FCV-1GW-105] Decay Tank Bleed Control Valve by placing

[AM-1GW-105] to MAN and raise output to 100%.

17. Verify [FR-1GW-105] GW Decay Tank Flow to injector does not exceed the maximum bleed flow rate of 2 cfm or the limit specified in the discharge permit.

18. Verify [PR-1GW-103] Decay Tank Pressure decrease for the decay tank being j l discharged. '

19. Verify response of [RM-1GW-108A,108B] Gaseous Waste Particulate and Gas Monitors.

20. Two hours after the discharge has been initiated, perform the following steps:

a. Confirm the bleed flow rate in units of SCFM by using the following equation:

Bleed Flow Rate = (132 cu. ft.) (Pi- Pf) (SCFM)

(14.7 psi) (Tf - Ti)

Where, Pi = initial decay tank pressure in PSIG from [PR-1GW-103]

Pf = current decay tank pressure in PSIG from [PR-1GW-103]

i Ti = time the discharge started

'\ Tf = current time

, (Tf - Ti) shall have units of minutes Bleed Flow Rate = (132 cu. ft.) ( PSIG - PSIG)

(14.7 psi) ( min. - min.)

Bleed Flow Rate = SCFM

b. If [FR-1GW-105] GW Decay Tank to injector is inoperative, then perfortn the following:

1) Use the above equation to determine the bleed flow rate.

Note: Steps 1 and 2 will need to be performed so that Radcon can obtain the sample.

2) Notify Radcon to obtain a grab sample.

l 3) Notify [PR-1GW-103] Decay Tank Pressure.

l

c. Contact the Shift Chemist and verify that proper Tritium sampling has been completed. If the proper Tritium sample has not been obtained, terminate the discharge and do not reinitiate until a Chemist is prepared to obtain the sample.

d. If the bleed flow rate exceeds 2 SCFM or the maximum bleed flow rate specified on the RWDA-G, then stop the discharge by performing Steps 21.a through 26 and notify Radeon of the problem.

Bnaver Valley Power Station Unit i 10M-19.4.E(ISS3) l Gaseous Waste Disposal System issue 3 Revision 2 Operating Procedures )

Page E 5 of 6 i DECAY TANK DISCHARGE l

l 21. When [PR-1GW-103] Decay Tank Pressure decreases to 5 PSIG to 2 PSIG, or a  ;

I pressure greater than 5 PSIG when specified by the NSS, stop the discharge as l l follows:

a. Close [FCV-1GW-105] Decay Tank Bleed Control Valve by placing

[AM-1GW-105] to MAN and set output to 0%. I

b. Close [TV-1GW-103] GW Decay Tank to CTWR Viv.

l c. Close [TV-1GW-103A2 (103B2) (103C2)] 1 A (1B) (1C) GW Decay Tk Bleed Valve for the decay tank just discharged by placing its FILL-OFF-BLEED selector

! switch to OFF.

1) Independently Verify that [TV-1GW-103A2(103B2)(103C2)],1 A(18)(1C) GW

Decay Tk Bleed Valve, are Closed AND Document in 10M-54.2 S1-4(5)(6),

l Nuclear Control Operators Report.

22. Repeat Step 6 at the end of each discharge.

L

23. Record the DATE, TIME, decay tank pressure in PSIG and OPER INIT (the initials of the operator making these entries) on the RWDA-G at the end of each discharge.

1

24. Determine the TOTAL DISCHARGE TIME in minutes and record on the RWDA-G.

jJ i Note: The Rad Tech must enter the Control Room to reset the alarm setpoints on the  !

analog instrument and will initial the RWDA-G.

l l 25. Contact Radeon so that the Hi and Hi Hi Alarm setpoints can be reset in accordance l with the Radiation Control Manual.

i Note: The NSS/ANSS at Unit 1 and the NSS/ANSS at Unit 2 signatures denotes that only one batch RWDA-G was discharged at one time and that the appropriate alarms have been reset.

1

26. The NSS/ANSS at Unit 1 and the NSS/ANSS at Unit 2 shall review the RWDA-G to

! confirm that the data entered by the operator is complete and correct, sign and date the RWDA-G at POST.

REFERENCES i

Note: All references used prior to 04/30/87 are located in Section 5.

I

1. OMDR No. 87-0669,86-0652,85-573,87-0819,87-0900, OMCN 87-90. OCP 726,

, 8700-RM-43A, BVPS RCM Chapter 3, Procedure 6.6 (Revision 14).

2. OMCN No. 87-0130 (Revision 16).

3. OMDR No. 87-1012, 88-0842, 0857; Special Operating Order 87-8-1; ND1MTS:0573 (Revision 19).

4. OMDR No. 1-88-1850; SOO 87-8-1; NRC inspection Report 87-15 (Revision 21).

L - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ - . - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . _ . - - - - - - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ _ _

Besvar Valley Power Station Unit i 10M-19.4.E(ISS3)

Gassous Wasto Disposal Systern issue 3 Revision 2 Operating Procedures Page E 6 of 6

! DECAY TANK DISCHARGE S. OMDR Nos. 1-89-0443,1-90-0202 (Issue 3, Revision 0).

l l 6. OMDR 1-92-0563, OMCR 1-95-0504, Tech Spec. Amend.188, ODCM Appendix C, l OMCN 1-92-102, (Revision 1).

l 7. OMCN 1-96159 (Revision 2).

1 l

l l

1 f I l

_ _ _ - - - - - _ _ _ _ _ . - - _ . - - - - - - - _ - - - - _ - - - - - - - - - - I

i .

BVPS - AOP 10M-53C.4.1.10.1(ISS3A) I ll AOP N*r A0P Title Residual Heat Removal System Loss 3A 1.10.1 {ss i( ,

l l l

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RCS Hestup Rate With RCS Intact i And initial PRZR Level At 22%

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100 150 200 0 50 Time After Shutdown (Hours)

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1101-1 l

l-13 Of 18

--_- - _40 PILO!__0_3/19/96 _ _ _ _ ____ - - - - - - - ___. _ _ _ - . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _

BVPS - A0P 10M-53C.4.1.10.1(ISS3A)

AOP Nuiter A0P Title

{ Residual Heat Removal System Loss . Issue 3A 1.10.1 Revision 5

(-

l Attachment 2 RCS Heatup Rate With RCS Level One Foot Below h Flange And AR1hree Loopsisolated 10 l

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< 0 150 200 0 50 100 Time After Shutdown (Hours) 1 ('

1101 '

L 14 Of 18

- _____ AOP11_01 _03/19/9_6_

BVPS - A0P 10M-53C.4.1.10.1(ISS3A) l A0P T1tle i AOP Number Residual Heat Removal System Loss Issue 3A 1.10.1 Revision 5 l (

~

Attachment 3 BOIL-OFF RATE 140 130 I

120

t. toss or n m 110 s. coa.o v nnTeseepeNDENT  ;

, QF RCECOMERATON - -

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s M 40 45 50 0 5 10 15 20 25 30 35 TIME AR 2R SHUTDOWN (DAYS)

('

1101-3 l

^ 03 15 of 18

--___ 320l_.__ '@#88. _ _ _ _ _ _ . _ _ _ _ . _ _ _

BVPS - A0P 10M-53C.4.1.10.1(ISS3A)

AOP humber AOP Tttle Issue 3A Residual Heat Removal System Loss Revision 5

.. 1.10.1

(,

Attachment 4 WORKSHEET TO ESTIMATE TIME TO SATURATION .

1. Record saturation temperature corresponding with present RCS pressure.

F

2. Record present RCS temperature.

. F

3. Determine RCS heatup rate using Attachment 1 or 2.

F/ Min 4

4. Estimate time to saturation as follows:

+

(RCS saturation temp - RCS temp)

Time to saturation =

Heatup rate

~

Time to saturation =

F/ Min (Step 3)

I Time to saturation = Minutes l

-END-i t

I l

- _ --_____.__ADP1101 03/19/96

BVPS-EOP 10tA53A.1.F-0.4(ISS1B)

!i ISSUE 1B

{ F-0.4 VESSEL INTEGRITY RmSION 2 l

.P l

Au. RCS PRESSURE -

NO GO TO COLD LEG TEMPERATURE g,,g,gg pot 4TS HAVE REMAINED FR-R1 TO RJGiT OF UMtT A ygg

-- =, NO ...(3 =.;o TEMPERATURES l g l GREATER THAN YES 300F m RCS g l COLD LEG l

TEMPERATURES GREATER THAN YES 330F l

TEMPERATURE CSF REDUCTION IN ALL NO 8 SAT RCS COLD LEGS LESS THAN 100F GO TO

/

I IN THE LAST 60 MINUTES YES f FR-P.1 ALL RCS NO COLD LEG i TEMPERATURES l GREATER THAN 300F YES RCS PRESSURE l NO LESS THAN COLD g O/ERPRESSURE $ GO TO LIMIT OF 410 PSIG YES gg p RCS l

gg _

TEMPERATURE ggp GREATER THAN SAT 330r l '

CSF SAT COLOR LINE CODE SYMBOL CODE RED M

_ee.... @

(3 GREEN 1OF1

I BVPS - E0P 10M-53A.1.2-G(ISSIB)

I Number Title Issue 1B Natural Circulation Verification s

2-G Revision 2

(

l i l A. PURPOSE

~

To provide a concise list of conditions which support or indicate natural circulation flow.

B. SYMPTOMS OR ENTRY CO@JTIONS When directed to verify natural circulation flow.

r lt

'f*(,

I

.e 4

O l

BVPS - E0P 10M-53A.1.2-G(ISSIB)

I k Number Iltle Issue 1B 2-G Natural Circulation Verification Revision 2

(

1. yerify Natural Circulation Bv Checkina The Followina Indications

a. RCS subcooling based on core exit TCs - GREATER THAN SUBC00L'ING LISTED ON ATTACHMENT 6-A

b. SG pressures - STABLE OR DROPPING

c. Either of the following:

e RCS Tavg - STABLE OR DROPPING

-0R-4

. RCS hot leg temperatures - STABLE OR DROPPING i

j d. Core exit TCs - STABLE OR DROPPING

e. RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG P

[

2. Natural Circulation May Be Enhanced By Raisino The Rate At Which Steam is Beina Dumoed

3. RETURN TO Procedure And Steo In Effect REFERENCES

1. Issue 1A, Revision 0: OM 1/2.538.1, Appendix A, E0P Writers Guide".

2. Issue 1A, Revision 1: Walkthrough Table-Top Validation; OMDR 1-89-1350.

3. Issue IB, Revision 0: Validation Connent (9/19/90).

- END -

I

\,

1A2G 2/12/97 2 of 2 C-- - _ _ _ _ - - - - . - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

BVPS - E0P 10M-53A.1.6-A(ISS16)

" Issue 1B 6 O F Plus Subcooling Based On Core Exit TCs g Revision 2 ICCM MINIMUM SUSC00 LING (F)

RCS PRESSURE COLUMN 1 COLUMN 2 (PSIG) NORMAL CNMT ADVERSE CNMT*

2400 25 41 l 2300 25 41 l 2200 25 41 l 2100 26 41 l 2000 26 42 l 1900 26 42 l 1800 26 42 l 1700 27 42 l 1600 27 43 l 1500 27 43 l 44

(.- 1400 1300 28 28 44 l

l 1200 29 45 l 1100 30 45 l 1000 30 46 l 31 47 .

l 900 800 33 48 l 34 50 l 700 600 36 52 l 500 39 54 l 400 43 58 l

• Adverse CNMT: CNMT pressure greater than 5.0 PSIG

-0R-CNMT radiation greater than 1E45 R/HR

-0R-Integrated CNMT radiation level greater than 1E+6 R k 1 l

_ _ __ _ ____ _._ _ __ __ _ __ B A @A 2/]2/97 1 of 2 ,

i

BVPS - E0P 10M-53A.I.6-A(ISSIB) i humber Title 0 F Plus Subcooling Based On Core Exit TCs Issue IB 6-A Revision 2

(,

I SPDS/PVC RCS SUBC00 LING (F)

RCS PRESSURE COLUMN 1 COLUMN 2 (PSIG) NORMAL CNMT ADVERSE CNMT* i 2400 23 38' l 2300 23 38 l 2200 23 38 l 2100 23 39 l 2000 24 39 l 1900 24 39 l 1800 24 40 l

- 1700 24 40 l 25 40 l

,(

1600 25 41 l 1500 26 41 l 1400

(. 1300 26 42 l

• - 27 42 l ,

1200 1100 27 43 l l 28 44 l l 1000 29 45 l 900

• 800 30 46 l i 32 47 l 700 34 49 l 600 500 36 52 l 40 56 l 400

• Adverse CNMT: CNMT pressure greater than 5.0 PSIG ,.

-0R-CNMT radiation greater than 1E+5 R/HR

-0R-Integrated CNMT radiation level greater than IE+6 R

- END -

1A6A 2/12/97 2 of 2 L_________________.

BVPS - E0P 10M-53A.1.5-D(ISSIB)

Number Title 5-D PTS - Operational Limits Curve Issue IB Revision 2 (l;

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DUQUESNE LIGHT COMPANY l

Beaver Valley Power Station l

Unit 1 l 10M-46.4. A l #s Hydrogen Recombiner Startup Issue 4 Revision 2 Date Pages issued Effective Date Prepared by L. R. Montanari 11/11/96 A1 through A5 . NOV 2 01995 Date Validated by Date Reviewed by

, C. O'Neill 11/12/96 N/A Date r e y Date OSC Meeting No.

OMCN 1-96-356 { g,3 , fg g i

CONTROLLED HPS UNOT 1

i Beaver Valley Power Station Unit 1 10M-46.4. A

, Post-DBA Hydrogen Control System Issue 4 Revision 2 Operating Procedures Page A 1 of 5 l

(

Hydrogen Recombiner Startup

1. PURPOSE This procedure describes the startup of the Post DBA Hydrogen Recombiner following the unlikely occurrence of a loss of coolant accident. This is accomplished by first setting up the Hydrogen Analyzer arid monitoring Containment hydrogen concentration. When the concentration level reaches a preset value, the Hydrogen Recombiner is aligned and started. This procedure is entered from an EOP.

II. PRECAUTIONS AND LIMITATIONS A. If hydrogen concentration is 2: 5%, concult TSC before placing Recombiners in operation.

B. During accident conditions, radiation levels may be high in the Recombiner area.

Limit the time spent in this area.

C. In order for the Hydrogen Recombiners to operate with sufficient flow, Containment pressure must be controlled as close as possible to -2 psig (13 psia). However, Containment pressure must remain below -2 psig (13 psia) to ensure Containment remains subatmospheric. ,

( 111. INITIAL CONDITIONS A. The EOPs require the Hydrogen Recombiners to be placed in service.

( B. The NSS has approved the performance of this procedure.

C. The 480 VAC distribution system is operable.

D. The following procedure is available:

1. 10M-46.4.G," Placing Wide Range Containment Hydrogen Monitoring System in Operation". .

IV. INSTRUCTIONS IN ote: Valves for the A Recombiner are given in procedure, valves for the B Recombiner are in parenthesis.

A. Place the Hydrogen Recombiner in Service ~

1. Contact Radcon to deterrrine what type of protective apparel is to be worn and any shiciding required.

2. Obtain the following keys to unlock [1HY-101,102,103,104,110,111,19C and 197].

a. SR/O.C.

b. SR/O.D.

l

l Beaver Valley Power Station Unit 1 10 M-46.4. A Post-DBA Hydrogen Control System Issue 4 Revision 2 j t Operating Procedures Page A 2 of 5 I

(

Hydrogen Recombiner Startup ,

3. Unlock AND Open the following valves with the reach rods located in West Cable Vault 735':

a. [1HY-101](LS), Recombiner 1 A Containment Upstream isolation (Key SR/O.C.)

b. [1HY-103](LS), Recombiner 1 A Containment Downstream isolation (Key SR/O.C.)

c. [1HY-102](LS), Recombiner 1B Containment Upstream isolation (Key SR/O.D.)

d. [1HY-104](LS), Recombiner 1B Containment Downstream Isolation (Key j

SR/O.D.)

4. Verify the following Containment Vacuum Pump trip valves are Closed (BB-A):

a. [TV-1CV-150A],1 A Cnmt Vac Pump Cnmt Isol Viv

b. [TV-1CV-150B],1 A Cnmt Vac Pump Cnmt isol Viv

c. [TV-1CV-150C],18 Cnmt Vac Pump Cnmt isol Viv k d. [TV-1CV-150D],1B Cnmt Vac Pump Cnmt Isol Viv

5. Unlock AND Open the following valves located in the Main Steam Valve Room 752':

{

a. [1HY-110](LS), Recombiner 1 A Containment Return isolation (Key SR/O.C.)

b. [1HY-196](L3), "A" H2 Recombiner Outlet isol (Key SR/O.C.)

c. [1HY-111](LS), Recombiner 18 Containment Return isolation (Key SR/O.D.)

d. [1HY-197](LS), "B" H2 Recombiner Outlet Isol (Key SR/O.D.)'

- 6. Start up both [H2A-1HY-101 A and 101B], Wide Range Hydrogen Analyzers, to monitor the Containment Dome in accordance with 10M-46.4.G," Placing Wide Range Containment Hydrogen Monitoring System in Operation".

7. When the [H'2A-1HY-101 A and 101B], Wide Range Hydrogen Analyzers, indicate hydrogen concentration inside Containment at levels ir which the.EOPs require the Hydrogen Recombiners to be started, perform the following:

a. Turn on [MCC1-ES(E6) Cub BN(BU)], labeled "1HY-RT-1 A(B) Hydrogen Recombiner via SAF-SW-68(69)", located in the West (East) Cable Vault,735, ,

Safeguards.

b. Close [MCCi-ES(E6) Cub AQ(BR)], MOV-1HY-101 A(101B) Cnmt Atmosphere Purge Blower 1HY-P-1 Suction isolation Viv, located in the West (East) Cable Vault.

{

1 l

Beaver Valley Power Station Unit 1 10M-46.4.A

Post-DBA Hydrogen Control System issue 4 Revision 2 Operating Procedures Page A 3 of 5 l (

l Hydrogen Recombiner Startup

c. Verify the following valves are Closed from the HCP Panel Post UBA Hydrogen Control Panel, located in Safeguards 752':

1) [MOV-1HY-101 A(101B)] Cnmt Purge Blower inlet isolation A(B)

2) [MOV-1HY-103A(103B)] Purge Air inlet isolation A(B)

d. Open the following breake;3:

1) [MCC1-ES(E6) Cub AQ (BR)] MOV-1HY-101 A(1018) Cnmt Atmosphere Purge Blower 1HY-P-1 Suction isolation Viv, located in the West (East) l J

Cable Vault.

2) [MCC-ES(E6) Cub AU (BT)],MOV-1HY-103A(1038) Hydrogen Analyzer H2A-1HY-100A(1008) Purge Air inlet isolation Viv, located in the West (East) Cable Vault.

e. Open [MOV-1HY-102A(1028)], H2 Recombiner 1 A(18) Inlet Isolation, from the HCP Panel Post DBA Hydrogen Control Panel, located in Safeguards 752'.

f. At [HY-CCA-1 A(18)] Power Control Cabinet A(B), depress AND hold down

[HS-1], START pushbutton for 10 seconds, located in Safeguards 752'.

I.

8. Close AND lock the following valves of the non-operating Hydrogen Recombiner, with the reach rods located in West Cable Vault 735':

( a. [1HY-102(101)](LS), Recombiner 18(1 A) Containment Upstream Isolation (Key SR/O.D.(0.C.))

b. [1HY-104(103)](LS), Recombiner 1B(1 A) Containment Downstream Isolation (Key SR/O.D.(0.C.))

9. Close AND lock the following valves of the non-operating Hydrogen Recombiner, located in the Main Steam Valve Room 752':

I

a. [1HY-111(110)](LS), Recombiner 1B(1 A) Containment Return isolation (Key S R/O.D.(O.C.))

b. [1HY-197(196)](LS), Recombiner "B"("A") Hz Recombiner Outlet isol (Key SR/O.D.(0.C.))

10. Independently Verify the positions of the valves which were closed in the above steps 8 and 9 AND document the verification in 10M-54.2 St-4(5)(6), Nuclear Control Ope 4 alors Report.

4 I

Beaver Valley Power Station Unit 1 10M-46.4. A Post-DBA Hydrogen Control System issue 4 Revision 2 Operating Procedures Page A 4 of 5

(

Hydrogen Recombiner Startup (

V. REFERENCES A. TECHNICAL SPECIFICATIONS

1. BVPS-1 T.S. 3.6.4.1

2. BVPS-1 T.S. 3.6.4.2 B. UPDATED FINAL SAFETY ANALYSIS REPORT

1. UFS AR-1 Section 6.5-1

2. UFSAR-1 Figure 6.1-1

3. UFSAR-1 Figure 6.5-1 C. COMMITMENTS NONE D. ADMINISTRATIVE NONE E. VENDOR INFORMATION f-7 ~

1. 8700-04.031-0012, Thermal Hydrogen Recombiner System

2. 8700-07.531-0026, instruction Manual Hydrogen Containment F. DRAWINGS

1. 11700-LSK-27-13A, Post DBA - Hydrogen Control System

2. 11700-LSK-27-13E, Post DBA - Hydrogen Control System

3. 8700-RE-1S,480V One Line Diagram SH 11

4. 8700-RE-1T,480V One Line Diagram SH 12

5. 8700-RE-1 AK,120V AC One Line Diagram SH 5

6. 8700-RM-446-1, VOND Post DBA Hydrogen Control System

< 7. 8700-RM-446-2, VOND Post DBA Hydrogen Analyzer System

8. 8700-RM-412-1, VOND Cont Vacuum & Leakage Monitoring O. OPERATING MANUAL

1. 10M-46.4.G. Placing Wide Range Containment Hydrogen Monitoring System in l Operation

2. 10M.46.31HY Valve List i

3. 10M.46.3 Power Supply and Control Switch List H. PLANT MODIFICATION

1. DCP 621, Environmental Qualification Modification for Hydrogen Recombiners I

Beaver Valley Power Station Unit 1 10M-46.4. A Post-DBA Hydrogen Control System issue 4 Revision 2 l Operating Procedures Page A 5 of 5 lg Hydrogen Recombiner Startup t

1. OTHER f

1. OMDR 1-94-0465 (Issue 4, Rev.1) l

2. OMCN 1-96-356 (Rev. 2).

I i

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4 E

i

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Record Type #A9.3308 g

i DUQUESNE LIGHT COMPANY Beaver Valley Power Station 4

Unit 1

?O 3 TRA N NG USE C.

i

. 1 l

10M-39.5.B.6 i i

( TABLE 394125V DC SYSTEM LOADS k

issue 4 Revision 5 ,

Prepared by Date Pages issued Effective Date R. Plummer 09/30/97 1 thru 28 @ 2 1 1997 Reviewed by Date validated by Date F. J. Schaffner 09/30/97 N/A OSC Meeting No. Date A na:Wed by Date Non-Intent 09/30/97

/D-8'47

/

1

(

CONTROLLED BVPS EDT1

B:cv;r Vall:y Pr,wtr Station Unit 1 10M-39.5.B.6 125V DC Control System issue 4 Revision 5 Figures and Tables Page 1 of 28 TABLE 39-6125V DC SYSTEM LOADS Note:

• Components that list alternative normal system arrangements shall have the as-left position circled when position verifications are performed and initialed.

• Names and initials foi operators performing load list verifications.

FULL NAME INIT. FULL NAME INIT. FULL NAME INIT.

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To: Tom Kenny- USNRC From: Rich Brooks, Duquesne Light Co. [

Date: March 20,1998

Subject:

Beaver Valley Power Station, Unit 1 - Initial Exain Materials The following materials are being submitted to you 1.. review, comment, and approval for the BVPS Unit 1 NRC Imtial License Examination scheduled for the week of April 20,1998.

This submittal is in accordance with the instmctions in Rev 8 of NUREG-1021, " Operator Licensing Examiner Standards."

1. Operating Test Drills (4)

2. Operating Test JPMs (14 JPMs & I set of Admin questions.)

3. Exam Maierials History (page 2 of this memo)

4. Quality Assurance Checklists *

• Form ES-301-6, " Competencies Checklist," and ES-301-5 " Transient and Event Checklist" will be filled out and submitted during the exam walkdown week when the drills are selected and the crew members have been assigned.

We request that these materials be withheld from public disclosure until after the completion of the examination.

If you have any questions or require further information, please contact me at (412) 393-5755.

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Exam Materials History Drills-All four drills submitted are new.

JPMs Part A: There are 4 Admin JPMS, and I set of Admin questions.

Part B: There are 10 JPMS. 3 JPMs are new,2 JPMs are Alternate Path.

Exam Outline

~t The Exam Outline that was sent to you on February 20,1993 has been revised as described in the front of each outline.

Validation All exam material submitted has been validated by a Licensed operating crew and the exam team.

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k 1. Quality Assurance Checklists.. . ,

, .1 1.1. Operating Test Checklist (ES-301-3) 1.2. Simulator Scenario Quality Assurance Checklist (ES-301-4)

2. Category A- Administrative Topics 2.1. Category A Outline. .. .. .. . . . .2 2.2. - A Perform QPTR JPM... ... . . . . . .. .. , . . .3-2.3. A Temporary Operating Procedures Questions . . . . . . - . . .. . .. 4 2.4. A 2 - Review Acceptance Criteria JPM . .. . .. . .. .. .5 2.5. A Determine Allowable Exposure JPM.... .. .. .. . 6

' 2.6. A Emergency Classification JPM., . . . . . . . . . .7 j

3. Category B - Control Room Systems and Plant Walkthrough ,

- 3.1. Category B Outline . . . . , . .8 3.2. Control Room JPMs 3.2.1, RWST Makeup Using Blender JPM , . .. . .. .. 9 3.2.2. Align S1 Pumps for 11ot/ Cold Leg Recirculation JPM.. . . . .

.10 i 3.2.3. Place Overpressure Protection System in Service JPM.. . .1I 3.2.4. Monitoring AFW Pump Performance During Loss ofInstrument Air JPM . .. , .12 j 3.2.5. Control Room Evacuation JPM.. . . . .13

{ . 14 3.2.6. Intermediate Range NI Functional Test JPM . -. . . .

l 3.2.7. Response to Containment Flooding JPM.. . . . . .. .15' l

3.3. In-Plant JPMs -

3.3.1. Response to Loss AFW Pump Suction Flow JPM.. . . .16 3.3.2. Locally Start the Emergency Diesel Generator JPM.. , .17-i 3.3.3. Transfer to Cold Leg Recirculation JPM . . . .., . 18

4. Category C - Integrated Plant Operations l 4.1. Scenario 1... . . . .. . . . . . . .. .19 4.2. Scenario 2.. .. .

. .. . .20 4.3 Scenario 3.. . .21 4.4. Scenario 4.. . . . . , . . . . .22 l

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Notes for ES-301-4, Simulator Scenario Qualit' Assurance Checklist.

1. Counted Instrument Failure Procedures as Abnormal Operating Procedures. l

2. Form ES-301-5 and ES-301-6 have not been completed because the three scenarios that will be  ;

utilized for the actual examination have not been identified.

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Notes for ES 3013, Operating Test Checklist

l. Written examination is not complete at the time of Operating Test Submission. }

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l Category A - Administrative Topics Changes

'i e Replaced Topic A-4 with Emergency Plan Classification JPMs.

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ES-301 Administr5tive Topics Outline Form-ES-301 1 Facility; Beaver Valley 1 Date of Examination: 4/20/98 Examination Level: SRO-1 Operating Test Number: I l' Administrative Describe method of evaluation:

Topic / Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions AI Conduct of Operations - Plant JPM - Perform a QPTR Giving Out of Spec Value Parameter Verification / QPTR K/A: 2.1.7 [4.4] l Procedure Control Question: Tracking in use Temporary Operating Procedures K/A: 2.2.6 [3.3]

Question: Review and approval of a Temporary Operating Procedure K/A: 2.2.6 [3.3]

l A2 Surveillance Testing JPM: Evaluate a completed surveillance K/A: 2.1.12 [3.4]

l-l A.3 Emergency Exposure JPM: Approve Emergency Exposure per EPP/IP 5.3 l KA: 2.3.1 [3.0]

i A.4 Emergency Plan JPM: Perform Emergency Classification following Scenarios KA: 2.4.40 [4.0]

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l NUREG-1021 Interim Rev. 8. January 1997 File Name: Outline _revl. doc Time and Date Printed: 3/16!98 4:24 PM Prepared by WD Associates,Inc.

L_ _ - - - - - _ _ - - - - , - - - - - - - - - - _ _ _ -_a - - - - - - - - - - - - - - - - - . - - - - - - - - - - - _ - - - - - - - - - - - - - . _ - - . _ . - - - - - _ _ _ - - . - - - - - - _ _ _ _ - - - - - - - - - - . - - - - - _ _ _ - . - - - - _ _ _ , - - _ - _ - _ _ - _ _ - . _ - - - - - - - - - - - , - _ .--\

Nuclear Group l Trainirg Administrative Manual 03T CHECKLIST /JIN 03VER PAGE DRIGINAL PROGRAM TITIE: Licensed Operator Training (Retraining)

SUBDIVISION: On-the-Gob Training 03T CHECKLTST/JPM TITIE: Perfonn A Quadrant Power Tilt Calculation JPM NO.: 1CR-003 COMPUI'ER 00DE: N/A Revision No. Date Revision No. Ibte f~

l 02/13/90, 2 07/09/90 1 08/12/91 4 chv/n ,

5 10l93lY)

PREPARED BY: 'Ihomas Gillot  % DATE: 10/12/88 l

l APPROVED IDR IMPLEMEr7FATION: /

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Director, Operations Training, or Designee l

DUQUESNE LIGfT OCMPANY  ;

j Nuclear Group Training Administrative Manual I.ESSON PIAN AND G7T REVISION APPROVAL SHEET DOCUMEh7P TITLE: Perform A Ouadrant Power Tilt Calculation Revision Anoroval I No. Brief Description Revised by: Sionature Date 1 Revised to new format. T. Gillot Deleted report back .

/

requirements. Changed Step 1 i to critical. Revised to .  ? C' reflect that the method of calculation is critical and .

not the math. l 2 Updated to reflect current A. Beckert procedure revision. Updated 7 g $geMi to incorporate Operations 1M l Exarn conunents. // f) 3 Changed variables. Added new T. Gaydosik Df#v/146 el d k ,

cover page. Delete attached g, 4 gjgj l questions.

4 Updated to latest JPM format.

Added two questions to JPM. [%

R. Bretton M p/fy/g

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5 Revised to reflect the R. W. Li d >

deletion of OM1.49.4.G and the A7 '

m implementation of replacement d lo[M [97 procedure 10ST-2.4A.

Increased time allotted.

Time revalidated against new procedure.

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RTL #A5.640U BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET

{ JPM Number: 1CR-003 Rev: 5 System #: 015 JPM

Title:

Perform A Quandrant Power Tilt Calculation K/A

Reference:

015000 A4.02 3.9/3.9 Rev. O Task ID #:0150040201 015000 A1.04 3.5/3.7 Rev. 0 015A4.02 3.9/3.9 Rev. 1 015A1.04 3.5/3.7 Rev. 1 JPM Application: Requal Initial Exam O Training E. valuation Method LOCATION TYPE Perform Plant Site O Training

O Simulate Simulator Annual Requal. Exam Classroom OJT

,0 Initial Operator Exam Administered By: Other: 1 O sv-T NRC i O Other:

I[ Evaluation Results l Performer: Name: Employee No:

Results SAT Time (minutes)

O UNSAT* Allotted: 20 Actual:

Time Critical: 0 Yes X No Administrative JPM Faulted

• Comments (Required for UNSAT Evaluation) - .

Evaluation Results Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 Employee No:

Question #2 O O f Employee No:

• Comments (Required for UNSAT Evaluation).

Evaluator (Print). Organization:

Evaluator Signature Date:

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET

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JPM NUMBER: 1CR-003 JPM TITLE: Manual QPTR Calculation TASK STAN.: Quadrant Power Tilt Ratio manually calculated in accordance with 10ST-2.4A.

RECOMMENDED STARTING LOCATION: CONTROL ROOM DIRECTIONS: You are to perform the task perform a ,

manual QPTR calculation INIT.-CONDITIONS: The plant is operating at 80*5 power. The plant computer is unavailable.

, INIT. CUE: Your supervisor directs you to Perform

(~ 10ST-2.4A. Quadrant Power Tilt Ratio Manual Calculation.

REFERENCES:

10ST-2.4A, Issue 4, Revision 1 TOOLS: NONE HANDOUT: 10ST-2.4A. Quadrant Power Tilt Ratio Manual Calculation Nuclear Instrument Current Readings QPTR Normalization Factors I

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RTL #A5.635.J l

t NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD  !

I (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

l Start time:

Candid' ate locates and revi4ws l 10ST-2.4A, Quadrant Power Tilt Ratio Manual Calculation. .

EVALUATOR CUE: Provide candidate with copy of f

10ST-2.4A with NSS/ANSS

1. ' approval signature.

1. Acknowledge performance 1. Candidate signs of procedure and sign procedure.

on.

COMMENT.'S : .

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Page 1 of 10 Revision:5

RTL #AS.635.J l

NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

2. Verify reactor power is 2. Candidate verifies being maintained at . reactor power is heing steady state value, maintained at steady state value.

EVALUATOR CUE: Power is being maintained at steady state value.

+

COMMENTS:

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RTL #A5.635.J

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NUMBER T5TLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3. Record power range 3. Candidate locates the detector QPTR . normalizatic factors normalization factors. in the Reactor Engineering Data Book and records power range detector QPTR normalization factors on Data Sheet 1.

l EVALUATOR CUE: Provide candidate with Data Sheet Three: (Sheet Three provides the following data to be recorded on Data Sheet one)

N41A= 0.0557 N41B= 0.0462 N42A= 0.0511 N42B= 0.0465 N43A= 0.0545 N43B= 0.0533 N44A= 0.0422, N44B= 0.0460 COMMENTS:

Page 3 of 10 Revision:5

RTL #A5.635.J k

NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

4.C. Record detector current values. EVALUATOR CUE: It is not ,

necessary to use DVM.

4.C Candidate reads current meters located on NI drawers and records data on

'q' Data Sheet. 1 EVALUATOR CUE: Provide candidate with the following values: (Sheet Two)

N41A= 94 N41B= 120 N42A= 104 N42B= 117 N43A= 96 N43B= 106 N44A= 116 N44B= 121 l

COMMENTS:

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l RTL #A5.635.J l i

NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

5.C Multiple each detector 5.C Candidate multiples reading by its - each detector. reading norn.alized value. by its normalized value and records in the " Current (Cor.)

column on Data Sheet 1.

./. EVALUATOR NOTE: The candidate

\ should record the following values:

N41A= 5.2358 N41B= 5.5440 N42A= 5.3144 N42B- 5.4405 N43A= 5.2320 N43B= 5.6498 N44A= 4.8952 N44B= 5.5660 COMMENTS:

Page 5 of 10 Revision:5

RTL #A5.635.J

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NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation i

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes-critical step) for Unsat.)

6.C Determine tilt ratio 6.1.C. Candidate adds the for each upper -

values for the .

detector. Current (Cor.) column and records the result in the space marked SUM:

EVALUATOR NOTE: The candidate should record the following

( value: 20.6774 6.2.C. Candidate divides the value in the SUM space by 4 and records the result in ,

the space marked KVG. I EVALUATOR NOTE: The candidate ,

should record the following l value: 5.1694 4 .

Page 6 of 10 Revision:5

RTL #A5.635.J

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NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

6.3.C. Candidate divides the value in the Current (Cor.) column for each detector by the value in the AVG space and records results in the " Tilt Ratio" column.

EVALUATOR NOTE: The candidate should record the following values:

N41A= 1.0128 N42A= 1.0280 i N43A= 1.0121 N44A= 0.9470 l

COMMENTS:

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Page 7 of 10 Revision:5

RTL #A5.635.J k

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NUMBER TITLE l ICR 's03 Perform a Quadrant Power Tilt Calculation l

l STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

1 7.C Determine tilt ratio 7.1.C. Candidate adds the for each lower . values for the ,

j detector. Current (Cor.) column

, and records the result in the space marked SUM:

EVALUATOR NOTE: The candidate l should record the following j l value: 22.2003 j 7.2.C. Candidate divides the value in the SUM space by 4 and records the , '

result in the space .

marked AVG. ,

EVALUATOR NOTE: The candidate should record the following value: 5.5501 l

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Page 8 of 10 Revision:5 l

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RTL #AS.635.J

{

NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

7.3.C. Candidate divides the

. value in the Curr,ent (Cor.) column for each detector by the value in the AVG space and records results in the " Tilt l Ratio" column.

EVALUATOR NOTE: The candidate should record the following values:

N41B= 0.9989 N42B= 0.9803 N43B= 1.0180 ,

N44B- 1.0029 COMMENTS:

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Page 9 of 10 Revision:5 u_-_-________

RTL #AS.635.J

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NUMBER TITLE 1CR-003 Perform a Quadrant Power Tilt Calculation STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3.C. Consult test criteria 8.C. Candidate identifies for acceptable . that N42A does not performance, meet acceptance criteria.

~

COMMENTS:

9. Inform NSS/ANSS of test 9. Candidate informs completion, supervisor that test is complete and that the test acceptance criteria is not met.

1 COMMENTS: -  !

. J EVALUATOR CUE: It is not necessary to complete the front cover sheet.

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STOP TIME:

I Page 10 of 10 Revision:5 l

I t._______._______ _ _ _ . . _ _

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RTL #AS.639.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET  !

f THIS SHEET TO BE GIVEN TO CANDIDATE

• l Read:

Task: Manual QPTR Calculation 1

l i

l INITIAL CONDITIONS: The plant is operating at 80% power. The plant computer is, unavailable. ,

INIT. CUE: lYoursupervisordirectsyoutoPerform10ST-2.4.A. I Quadrant Power Tilt Ratio Manual Calculation.

k.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM". -

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task Standard has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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s L_.__ .__ _ _. __ _ _ _ _ _ _ _ _

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DATA SHEET THREE N41A = 0.0557 .

N42A = 0.0511 N43A = 0.0545 N44A = 0.0422 N41B = 0.0462 N42B = 0.0465 N43B = 0.0533 N44B = 0.0460 l

1 6

1

I SHEET TWO - DETECTOR CURRENT READINGS N41 A= 94 N41B= 120 N42A= 104 N42B= 117 N43A= 96 N43B= 106 N44A= 116 N44B= 121 - ,

/.

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.r a , . ,_ ,

Record Type #A9.3308 DUQUESNE LIGHT COMPANY Beaver Valley Power Station ,

Unit 1 k.

10ST-2.4A ,

i i

I Quadrant Power Tilt Ratio Manual Calculation Issue 4 Revision 1 I

Prepared by Date Pagesissued Effective Date 08/27/96 1 through 10 SEP 0 51996 J. E. Burnecke Revie$ed by Date Validated by Date J.P.Keegan 08/27/96 t4/A .

Date Approved by Date OSC Meeting No.

Non-Intent 08/28/96 [jj g ((g _

f CONTROLLED

- [GDRlMT 1 _

Beaver Valley Power Station Unit 1 10ST-2.4 A issue 4 Revision 1 Operating Surveillance Test Page li i

Quadrant Power Tilt Ratio Manual Calculation Table of Contents

1. PURPOSE . . .............. ... . . .. . ...... . 3 .

II. DISCUSSION . . ............. . .. .. . ............... 3 Ill. ACCEPTANCE CRITERIA .. . . . .. .. .. . . ....... ... . 3 ,

1 4

IV. EQUIPMENT AND MATERIALS .. . . .... .... .... . .. 3 3

{

V. PRECAUTIONS AND LIMITATIONS ... .. . .. . .. 1 VI. iNITI AL CONDITIONS ... .. . . . . .. . . . . 3 Vll. INSTRUCTIONS .......... . ... ... .... .... 5 Vill. DATA SHEETG, TABLES, FIGURES AND ATTACHMENTS .... .... . 7 DATA SHEET 1 ............. . . . . . . . . 8 9 j ATTACHMENT A . . ... . .. . . . . .. . ....

i 10 IX. REFERENCES .. .. ..... . .... .. . .. .... .......

J CONTROLLED

-- o _

Bezvsr Vallsy Powcr Station Unit 1 10ST-2.4 A issue 4 Revision 1 Operating Surveillance Test Page 1 of 10 Quadrant Power Tilt Ratio Manual Calculation Frequency: W 00 Survel!!ance Requirements: 4.2.4(a)

Required for Mode (s): 10 Date / Time Completed: /

Performed in Mode (s): 1 Total Manhours:

TEST RESULTS: (Completed by Performer) PERFORMED BY:

- ame Wnt) InWal

) () or N/A) ,

l e l~ O T,est Completed S SATISFACTORY j

O i'ioblems Encountered (See Problem Sheet) l l

J O Unscheduled / partial OST (explain) i-Reviewer Signature /Date STA Review /

NSS App'roval /

COMMENTS: (include Date and initials) .

i

)

O Comments continued on Problem Sheet i

O Above 50% of rated thermal power.

1 DD Required at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady-state operation when QPTR alarm f

is inoperable.

1 CONTR_OL_

- LED __

l l l I Beaver Valley Power Station Unit i 10ST-2.4 A issue 4 Revision 1 Operating Surveillance Test Page 2 of 10 l4 ,

l Quadrant Power Tilt Ratio Manual Calculation j i

OST PROBLEM SHEET See Page and Step No. for problem description. See below for corrective action, eg: MWR l l No., OMCN No., OMCR or Database change written or other.

l l

PAGE NO. STEP NO. DESCRIBE CORRECTIVE ACTION INITIALS DATE m,

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Beaver Valley Power Station Unit 1 10ST-2AA lssue 4 Revision 1 Operating Surveillance Test Page 3 of 10 Quadrant Power Tilt Ratio Manual Calculation {

l. PURPOSE To determine by manual calculation the Quadrant Power Tilt Rstio (QPTR) and verify that it does not exceed the limit given in Technical Specification 3.2.4.

11. DISCUSSION i This OST is routinely performed on a weekly frequency, above 50% reactor power, when the QP.TR alarms (ANN. A4-59(67), POWER RANGE LOW (HIGH) SETPOINT FLUX DEVIATION OR AUTO DEFEAT) are operable, as determined by 10ST-2.4," Quadrant Power Tilt Ratio Alarm. Check". The required test frequency is increased to every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when a QPTR alarm;i,s inoperable.

Ill. ACCEPTANCE CRITERIA -

Note: An exception to the Acceptance Criteria exists for physics testing (Tech Spec 3.10.2).

A. Quadrant Power Tilt Ratio (QPTR) does not exceed 1.02 (Data Sheet 1)(T.S. 4.2.4.a).

IV. EQUIPMENT AND MATERIALS A. A digital voltmeter (DVM), if determined to be necessary during OST performance.

V. PRECAUTIONS AND LIMITATIONS A. . Perform this OST every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with the QPTR alarm inoperable.

B. If it is suspected that the meter indication on the power range drawers is erratic due to static in the meter face, a DVM should be used to determine current values. The DVM measurement should be taken at the test Jacks on the front of the power range i drawers.

VI. INITIAL CONDITIONS A. Plant Status Chanaes This procedure does not affect plant status.

B. NSSIANSS Slan-on

1. A QPTR determination is desired to verify conformance to Technical Specification l 3.2.4.

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Beaver Valley Power Station Unit i 10ST-2.4 A Issue 4 Revision 1 Operating Surveillance Test Page 4 of 10

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Quadrant Power Tilt Ratio Manual Calculation CAUTION: IF POWER IS 2:75% AND ONE POWER RANGE HIG,H NEUTRON FLUX CHANNEL INPUT TO QPTR IS INOPERABLE, QPTR MUST BE VERIFIED AT LEAST ONCE PER 12 HOURS IN ACCORDANCE WITH TECHNICAL SPECIFICATION SURVEILLANCE 4.2.4.b, USING 1RST-3.4, "lNCORE ANALYSIS OF QPTR".

2 If one power range high neutron flux channel input to QPTR is inoperable, AND thermal power < 75% the remaining three power range high neutron flux

,- channels may be used for calculating QPTR.

E No other tests of the power range channels are being performed during this OST.

l 4. NSS/ANSS verifies the following:

l l

• Section VI.A. Plant Status Changes, has been reviewed.

• Requirements of Section VI.8, NSS/ANSS Sign-on have been verified.

• Performance of this procedure is authorized.

DATE: TIME: CURRENT PLANT MODE:

(

NSS/ANSS COMMENTS:

/

a NSS / ANSS Signature C. Reactor Operator Slan-on

1. Reactor Operator performs the following:

• Acknowledge performance of this procedure.

Reactor Operator Signature D. Procedure Performer initial Conditions

1. Reactor power is being maintained at a steady-state value.

I initial / Date

2. Operator (s) performing this procedure has reviewed this procedure.

/

1. , initial / Date

/

Initial / Date

Beaver Valley Power Station Unit 1 10ST-2.4 A Issue 4 Revision 1 Operating Surveillance Test Page 5 of 10 Quadrant Power Tilt Ratio Manual Calculation Vll. INSTRUCTIONS

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A. Test Preparation

1. Record the power range detector QPTR normalization factors, found in the Reactor Engineering Data Book, Data Sheet 3 of 1RST-2.3," Nuclear Power Range Calibration". Data Sheet 5 of 1RST-2.4, " Alignment of Excore Instrumentation for

. Startup After Reload" OR Data Sheet 3 of 1RST-2.9, "NIS Single Point Calibration" l

. (NSS Office), on Data Sheet 1.

-~ j

.  ; initial / Date B., dPTR Determination Note: If one power range high neutron flux channelinput to QPTR is inoperable, AND thermal power < 75%, the remaining three power range high neutron flux channels may be used for calculating QPT.t. In this case, the entries on Data Sheet 1 for the OOS detector should be marked "N/A".

1. Record detector current values for each of the power range detectors in the

" Current (Uncor.)" column of Data Sheet 1, using either of the following methods:

(..

a. Detector current meters located on the power range drawers.

I

- Initiall Date Note: If uncertainty exists in reading the current meters, a DVM should be used to obtain the current readings. +

b. Test Jacks located below the meter faces using a DVM, in accordance with Attachment A.

Initial / Date

2. Multiply each of the detector current readings by its associated normalization factor AND Record the result in the " Current (Cor.)" column of Data Stieet 1. ,

i I  ;

Initial / Date

3. Perform the following for the Upper Detectors on Data Sheet 1:

a. Add the values in the " Current (Cor.)" column AND Record the result in the l space marked " SUM".

/

initial / Date

j Beav< r Val ley Power Station Unit 1 10ST-2.4 A issue 4 Revision 1 Operating Surveillance Test Page 6 of 10 Quadrant Power Tilt Ratio Manual Calculation

b. Divide the value in the " SUM" space by 4(3) AND Record the result in the space marked " AVG". .

I initial / Date

c. Determine the Tilt Ratio for each of the upper detectors by dividing each value in the " Current (Cor.)" column by the value of " AVG" AND Record the results in the " Tilt Ratio" column.

i.

/

Initial / Date N. Perform the following for the Lower Detectors on Data Sheet 1:

a. Add the values in the " Current (Cor.)" column AND Record the result in the space marked " SUM".

I initial / Date

b. Divide the value in the " SUM" space by 4(3) AND Record the result in the

_- . space marked " AVG".

l l Initial / Date

c. Determine the Tilt Ratio for each of the lower detectors by dividing each value in the " Current (Cor.)* column by the value of " AVG" AND Record the  !

results in the " Tilt Ratio" column.

I i Initial / Date

5. If uncertainty exists with the calculated tilt values, Request the Tilt Review Map from the IPC AND Compare the map with the results of this OST. l I

initial / Date C. Test Completion

4. Consult the Acceptance Criteria for acceptable performance.

I initial / Date

2. Inform the NSS or ANSS of the completion of this test.

I

/ Initial / Date

3. Complete the front cover sheet.

I Initial / Date

Bsaver Valley Power Station Unit i 10ST-2.4 A lssue 4 Revision 1 Operating Surveillance Test Page 7 of 10 Quadrant Power Tilt Ratio Manual Calculation Vill. DATA SHEETS, TABLES, FIGURES AND ATTACHMENTS

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A. Data Sheets

1. Manual QPTR Calculation B. Tables NONE C. Fiaures ,

NONE D. Attachments

.1. Use of DVM to Obtain Current Readings .

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Beaver Valley Power Station Unit 1 10ST-2.4 A ,

issue 4 Revision 1 i Operating Surveillance Test Page 8 of 10

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l Quadrant Power Tilt Ratio Manual Calculation DATA SHEET 1 MANUAL QPTR CALCULATION UPPER DETECTORS

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Norm Factor Current (Cor.) Tilt Ratio l l ' Current (Uncor.)

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l lN41A

• l lN42A l

lN43A N44A _ _ - __ _ _ _

SUM AVG LOWER DETECTORS Current (Cor.) Titt Ratto l l Current (Uncor.) l Norm Factor l l '

l l l lN41B l l l l )

lN428 l l l l lN438 l Performed By __/ / (init/TimelDate)

Verifled By _ / (Init/Date) l -

Beaver Valley Power Station Unit 1 10ST-2.4 A issue 4 Revision 1 Operating Surveillar..e iest Page 9 of 10 b ,

Quadrant Power Tilt Ratio Manual Calculation l l

ATTACHMENT A USE OF DVM TO OBTAIN CURRENT READINGS A. 5{gn-out the following M&TE equipment: ,

1. Digital Voltmeter (DVM), Fluke Model 45 or equivalent.

,- l'nstrument Number Cal. Due Date / / ,

I Initial / Date B. Set the following controls on the DVM:

1. Set Function to VDC.

I initla! / Date )

i

2. Set Range to AUTO.

I initial / Date CAUTION: DO NOT SHORT TEST JACKS TO GROUND - CHANNEL TRIP MAY OCCUR.

C. Insert the DVM leads into the Detector A(B) Test Jacks located at the bottom of the Power Range B Drawer.

.. I in'itial / Date D. Multiply the DVM reading by 1000 to obtain the detector current, (Example: 0.269 VDC x 1000 pA/VDC = 269 pA).

/

Initial / Date E. Record the detector current values to at least the nearest pA in the " Current (Uncor.)"

column of Data Sheet 1.

I initial / Date

Beaver Valley Power Station Unit 1 10ST-2.4 A Issue 4 Revision 1 Operating Surveillance Test Page 10 of 10 Quadrant Power Tilt Ratio Manual Calculation IX. REFERENCES A. TECHNICAL SPECIFICATIONS

1. 3.2.4  ;

2. 3.10.2 B. UPDATED FINAL SAFETY ANALYSIS REPORT kONE -

C: COMMITMENTS .

I NONE D. ADMINISTRATIVE NONE E. VENDOR INFORMATION NONE

[-

F. DRAWINGS NONE G. OPERATING MANUAL

- 1. 10M-49.4.G, " Quadrant Power Tilt Ratio" l

2. 10M-49.3, " Checklist G.1" ,

H. PLANT MODIFICATION I

NONE

l. OTHER

1. PR 2-95-247, LER 2-95-005; OMCR 195-0693 (Rev. 0)

2. OMCR 1-96-0939 (Rev.1) , j

A. I .2 Question 1 A Temporary Operating Procedure (TOP) is in effect for operation of the CVCS.

1. Where is the status of this TOP required to be tracked?

2. What information is required to be tracked concerning the TOP 7 ANSWER:

1. The NSS Tumover Checklist.

2. Any conditions or restrictions related to the TOP or to any jumpers installed by a TOP shall be noted. Conditions and restrictions may include mode change restraints, reactor vessel or refueling cavity levels, and ambient or river conditions.

Time Allotted: 10 mHutes KA: 2.2.6 (3.3)

Reference:

Control of Operating Procedures,1/20M-48.2.B, page 6, Issue 4, n v 10.

Comments:

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l l q ' THIS SHEET TO BE GIVEN TO CANDIDATE

• l- ' A.I.2 Question 1

~ A Temporary Operating Procedure (TOP) is in effect for operation of the CVCS.

1, Where is the status of this TOP required to be tracked?

. 2. What information is required to be tracked concerning the TOP 7 I

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. . . _ _ _ _ _ _ _ . - _ _ - - - - - _ . _ _ _ J

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A. I .2 Question 2 The Temporary Operating Procedure (TOP) that is in place for operation of CVCS requires an inent change because it will not work as written. The TOP was originally reviewed by the OSC and approved by the GMNO. Plant conditions require the TOP to be used in order for letdown to rernain in service.

1. How would the TOP be changed?

2. What level of review and approval would be required?

ANSWER:

1. By processing an on the spot change to the TOP. It will follow the same process as an On-the-Spot change to the operating procedure.

2. It will be required to be reviewed by the OSC and approved by the GMNO because it is an intent change.

Time Allotted: 10 minutes KA: 2.2.6 [3.3]

Reference:

Control of Operating Procedures,1/2OM-48.2.B, Issue 4, Rev 10, page 7 and 10

', Comments:

i

• THIS SHEET TO BE GIVEN TO CANDIDATE

• A. I .2 Question 2 The Temporary Operating Procedure (TOP) that is in place for operation of CVCS requires an intent change because it will not work as written. The TOP was originally reviewed by the OSC and approved by the GMNO. Plant conditions require the TOP to be used in order for letdown to remain in service.

1. How wou!d the TOP be changed?

2. What level of review and approval would be required?

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RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE l PROGRAM TITLE: Licensed Operator Training l SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Review the Acceptance Criteria JPM NO.: WD-ADM2 COMPUTER CODE: N/A l

Revision No. Date Revision No. Date l

l l

l PREPARED Ba' DATE:

l APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee 1

1 Revision 9

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RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l

LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Review the Acceptance Criteria Revision Approval  ;

No. Brief Description Revised by: Signature Date i

1 l

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Revision 9 1

L_________________.____. _ _ _ _ . _ _ _ _ _ _ _ _ _ , _

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: WD-ADM2 Rev: System #: Faulted: O JPM

Title:

Review the Acceptance Criteria K/A

Reference:

2.1.12 [3.4) Task ID #:

JPM Designation: O NO O RO @ SRO JPM Application: X NRC E Initial Exam O Training Evaluation Method LOCATION TYPE O Perform X Plant Site O Training

@ Simulate X Simulator O Annual Requal. exam O Classroom O OJT X Initial Operator Exam Administered By: O Other:

O Bv-1 O NRC O Other:

Evaluation Results

( Performer: Name: Employee No:

Results O SAT Time (minutes)  !

O UNsAT* A: lotted: 20 Actual:

Tine Critical: O Yes E No

• Comments (Required for UNSAT Evaluation):

Evaluation Results O Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No: _ . ,

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 N/A O O )

Employee No:

Question #1 _

N/A O O Employee No:,_

• Comments (Required for UNSAT Evaluation):

l Evaluator (Print): _ Organization:

Date:

Evaluator Signature Revision 9

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l RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l

! CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

l Task- l Review completed OST acceptance criteria.

INITIAL LOST-24.2, Motor-Driven Auxilliary Feed Pump Test -

[lFW-P-3A] Operability Test has just been CONDITIONS ~-

completed at power. The STA has reviewed the OST i for completeness but has not verified the acceptance criteria have been met.

INIT. CUE: Ensure the acceptence criteria have been met and identify any problems that have been encountered.

s l At this time, ask the evaluator any questions you have on this JPM.

i When satisfied that you understand the assigned task, announce "I am now beginning the JPM". ,

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observatier.s.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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i Revision 9

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RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER: WD-ADM2 JPM TITLE: Review Acceptance Criteria for OST I

1 RECOMMENDED Control Room / Simulator L I

STARTING LOCATION:

DIRECTIONS: Review completed OST acceptance criteria.

1 INIT. CONDITIONS: LOST-24.2, Motor-Driven Auxilliary Feed Pump Test [1FW-P-3A) Operability Test has just been completed at power. The STA has reviewed the OST for completeness but,has not verified the acceptance criteria have been met.

TASK STAN.: Review the acceptance criteria to ensure i '- they have been met and identify any acceptance criteria that have not been met.

INIT. CUE: Ensure the acceptance criteria have been met: and document any problems that have

- been. encountered.

REFERENCES:

LOST-24.2, Issue 2 Rev 15.

TOOLS: .None HANDOUT: Completed LOST-24.2.

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, Revision 9 I h

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RTL OR5.635.J NUMBER TITLE WD-ADM2 Review Acceptance Criteria i

STEP- STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

START TIME:

EVALUATOR CUE: Provide the applicant with the completed OST-24..

1.C Verify [1FW-P3A) AFW 3A 1.1C Checks Data Sheet 1 for Pump, operates within the IST data. Determines requirements of ASME XI, that required IST Program differential pressure is 10 psid low.

i.

i Comments:

2.C Verifies the Turb AFW pump 2.1 Verify Data Sheet No. 2 is complete.

tlFW-P-2) vibration 2.2C Identify that Pump readings are within acceptable ASME Section XI Outboard (1) Vertical IST Program values. vibration reading is in the Alert range.

Comments:

Revision 9

RTL #A5.635.J ,

i NUMBER TITLE WD-ADM2 Review Acceptance Criteria STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.) ,

3. Verifies Valves [1FW-37 3. Verifies Steps 8. 18 and and 40], A& B Header 19 are complete.

Disch Isol for [lFW-P-3A], i are exercised through one complete cylce of travel as required by ASME Section XI, IST Program Comments:

4. Verifies check valvee 4. Verifies Data Sheet ,

i

[1FW-51 and 69] are temperature of pump partial stroke exercised bearing outlet oil piping  !

open as verified by pump is 5 155 F.

l bearing disch oil piping temperature remained 5 155 F. .

Comments:

5. Identifies noted problems 5. Problems in acceptance

! on OST Problem Sheet criteria 3 and 6 are listed on OST Problem sheet.

Comments:

Revision 9 N __________ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

RTL #A5.635.J

~

I NUMBER TITLE WD-ADM2 Review Acceptance Criter'ia l

i STEP STANDARD i (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

6. Mark the Test Results as 6. Test Results marked as Problems Noted problems noted.

Comments:

STOP TIME I

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Revision 9 e______-____-_______-_________-____-_

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual l

OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training i

SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Determine Emergency Exposure Limit i

JPM NO.: WD-ADM1 l

COMPUTER CODE: N/A Revision No. Date Revision No. Date j I

t I

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee i

l t

i Revision 9 l

l

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division l Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Determine Emergency Exposure Limit Revision Approval No. Brief Description Revised by: Signature Date I i

1 1

1

< 1 1

1 4

i e

1 4

I Revision 9  !

u- .- I

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: WD-ADM1 Rev: System #: Faulted: []

l JPM

Title:

Determine Emergency Exposure Limit K/A

Reference:

2.3.4 [3.1] Task ID #:

JPM Designation: [3 NO [] RO X SRO JPM Application: X NRC X Initial Exam [] Training Evaluation Method LOCATION TYPE

[] Perform X Plant Site [] Training Simulate X Simulator [] Annual Requal. Exam

[] Classroom [] OJT UU Initial Operator Exam

.lministered By: [3 Other:

[] BV-T

[] NRC

[] Other:

g; valuation Results Performer: Name: Employee No:

Results [3 SAT Time (minutes)

[] UNSAT* Allotted: 20 Actual:

Time Critical: [] Yes X No

" Comments (Required for UNSAT Evaluation):

' r .' _ .

Evaluation Results [] Check here if same as above .

Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 N/A [] []

Employee No:

Question #3 N/A [] []

Employee No:

• Comments (Required for UNSAT Evaluation):

Evsluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL #AS.635)J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

.f a s k - =lDeterminethemaximumallowablelimitsforexposure.

INITIAL During a reactor shutdown a leak occurred in the CVCS CONDITIONS, system. A break has occurred outside of containment on the charging line. MOV-lCH-289 and MOV-lCH-310 cannot be closed remotely. .It appears that check valve (lCH-31] has failed to seat. An Alert has oeen declared due to the loss of RCS inventory. Health Physics has determined high radiation exists in the vicinity of [MOV-lCH-289]. The Operations Support Center Supervisor has identified a mechanic and an operator to attempt to close the valves. Neither person is declared pregnant. The TSC has indicatet that if the leak continues off site PARE may be required. I will act as Health Physics and the two individuals who will enter the area in order to provide any required information.

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. i INIT. CUE: Determine the exposure limitation for the individuals )

to enter and attempt to close the [MOV-CH-289].  !

Request any additional information that is necessary to determine allowable exposure. i At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning'the JPM".

Simulate performance or perform as directed the required task.

Point to any indicator or comronent you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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h RE $0.63.J BEAVER VALLEY JO3 PERFORMANCE MEASURE 1 1.

EVALUATOR DIRECTION SHEET

.i JPM NUMBER: WD-ADM1 JPM TITLE: Determine Emergency Expasure Limit RECOMMENDED Control Room / Simulator STARTING LOCATION:

DIRECTIONS: Determine and approve allowable emergency

. exposure.

INIT. CONDITIONS: During a reactor shutdown a leak occurred in the CVCS system. A break has occurred outside of containment on the charging line. MOV-lCH-289 and MOV-lCH-310 cannot be closed remotely.

It appears that check valve (lCH-31) has failed to seat. An Alert has been declared due to the loss of RCS inventory. Health Physics has determined high radiation exists in the vicinity of [MOV-lCH-289]. The Operations Support Center Supervisor has identified a mechanic and an operator to attempt to close 1 the valves. Neither person is declared  ;

pregnant. The TSC has indicated that if the j leak continues off site Pl.Rs may be required.

I will.act as Health Physics and the two individuals who will enter the area in order to provide any required information.

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' TASK STAN: Determine the maximum allowable 'imits for l exposure. . I INIT. CUE: Determine-the exposure limitation for the individuals to enter and attempt to close the

[MOV-CH-289].

REFERENCES:

EPP/IP 5.3, Rev. 7 j TOOLS: None ,,

HANDOUT:

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I RTL #A5.635.J j l

1 NUMBER TITLE i

WD-ADM1 Determine Emergency Exposure Limit 1

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STEP -STANDARD (Indicate "S" for Sat. or "U"'

.("C" denotes critical step) for Unsat.)

1 START TIME:

1. Locate correct procedure. 1. Obtains EPP/IP 5.3.

Comments:

NOTE: Steps 2 through 7 follow flow path of Att. 1. The i- information can be obtained from other locations in the procedure.

2. Verify-that there is a 2. Identifies that an Alert declared emergency. has been declared.

Comments:

EVALUATOR CUE: An Alert was given in the' initial conditions.

Revision 9'

RTL #A5.635.J l NUMBER TITLE i

WD-ADM1 Determine Emergency Exposule Limit l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3. Verifies individuals are 3.1 Verifies with Health qualified as radiation Physics that the workers, have'been issued individuals are radiation <

BVPS Dosimetry and are not workers.

~ declared pregnant.

3.2 Verifies with Health Physics that the individuals have been issued dosimetry.

3.3 Verifies that neither person is declared pregnant.

1 Comments:

EVALUATOR CUE: Both individuals and are issued BVPS dosimetry.

4. Identify that the exposure is 4. Identifies that PARS may be necessary to mitigate exceeded if leak is not radioactive releases isolated.

comparable to EPA PAGs.

Comments: j EVALUATOR CUE: Initial Conditions l indicated that the PARS will be. i required if leak continues. l l

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RTL #A5.635.J NUMBER TITLE WD-ADM1 Determine Emergency Exposure Limit d

STEP STANDARD

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(Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

5. Determine if the individuals S.1 Asks if the individuals are are volunteers. volunteers.

Comments:

EVALUATOR CUE: The mechanic and operator indicate that they are reluctant to volunteer but will perform the task if directed.

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6. Determine if the people have 6. Verify with Health Physics been brir#ed. if they have been briefed.

Comments:

EVALUATOR CUE: Health Physics states that they have briefed the individuals.

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Revision 9

RTL #AS.635'.J

.I: NUMBER TITLE WD-ADM1 Determine P 3rgency Exposure Limit STEP STANDARD (Indicate "S" for Sat. or "U"

-("C" denotes-critical step) for Unsat.)

7.C Determine the. allowable dose. 7.C Determines that the allowable dose will be 25 rem TEDE, 75 rem lens of eye and 250 rem organ _CDE.

Comments:

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F0H i i ,, ... . ,.~._ONJ EPP/IP 5.3

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EMERGENCY EXPOSURE CRITERIA AND CONTROL l

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APPROVAL PAGE Intent Related Revision Yes X No IF YES OSC and Site Approval ,

OSC Meeting Number Date NOTE: The approval of this revision by the Onsite Safety Committee ensures the requirements of 10 CFR 50.54(q) have been considered and not compromised.

b Reviewed Director, Emergency Preparedness Date Approved Manager-Nuclear Safety Date IF NO Reviewed . { w /C D 20 f'r Director,' Emergency Preparedness / D' ate Approved & , ,

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Mar.ager-Nuclear Safety Date I

@@@{[@]y Rev.7 BU@E201'3 .

EPP/ Implementing Procedure EPP/IP 5.3 1

EMERGENCY EXPOSURE CRITERIA AND COhTROL ,,

0 EFFECTIVE INDEX Issue 8 Rev. O OSC Approved 3-12-87 Issue 9 Rev. 0 Non-Intent Related 10-9-90 1 Non-Intent Revision 11-21-91 2 Non-Intent Revision 12-29-92 Rev. 5 OSC Approved 12-2-93 6 Non-Intent Revision 11-15-94 7 Non-Intent Revision 12-1-95

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EMERGENCY EXPOSURE CRITERIA AND CONTROL '*

TABLE OF CONTENTS A. Purpose B. References C. Responsibilities D. Action Levels / Precautions E. Procedure F. Final Condition

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EPP/ Implementing Procedure EPP/IP 5.3 1

EMERGENCY EXPOSURE CRITERIA AND CONTROL l A. PURPOSE 1

This procedure provides guidance and criteria for dose limitation in situations where it may be necessary for individuals to exceed established exposure limits to save a life or to minimize the consequences of an accident. Authorization for such exposures is provided by 10 CFR 50.47(B)(11).

B. REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and Implementing Procedures.

2.0 ICRP Publication 26, " Recommendation of the International Commission on Radiological Protection" 3.0 ICRP Publication 28, "The Principals and General Procedures for Handling Emergency and Accidental Exposures of Workers"

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4.0 EPP 400-R-92/01 (and subsequent revisions), " Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" 5.0 Title 10, Code of Federal Regulations Part 20 6.0 Title 10, Code of Federal Regulations Part 50 7.0 . NUREG-0654/ FEMA-REP-1 " Criteria for Preparation and Evaluation of Radiolog,ical Emergency Response Plans and Preparedness in Support of Nuclear Power Plants."

8.0 BVPS Health Physics Manual 9.0 NUMARC, Implementation of the New EPA Protective Action Guides in Existing Emergency Programs 3

1 Rev.7 C _ _ . _ _ . _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ . _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . _ _ - _ _ . _ . _ _ _ . _ _ _ _ _ _ - . . _ _ _ _ _ _ . _ _ _ _ _ _ . _ . _ . _ _ . _ _ _ _ _ . _ _ _ _ _ ._-_________._____..-______.__m

EPP/ Implementing Procedure EPP/IP 5.3

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EMERGENCY EXPOSURE CRITERIA AND CONTROL C. RESPONSIBILITIFE The Emergency Director has the responsibility and authority to ensure that the radiation exposure of personnel performing functions necessary to contend with the emergency condition, are maintained As low As Reasonably Achievable (ALARA) and in keeping with the provisions of this EPP/IP. The Emergency Director is the only individual who may authorize dose extensions in excess of 10 CFR 20.

D. ACTION LEVELS / PRECAUTIONS / CRITERIA 1.0 ACTION LEVELS I1 An emergency condition at the Beaver Valley Power Station has resulted in radiation levels within the Station greatly in excess of normal levels which require special considerations for exposure control.

,_ 2.0 PRECAUTIONS 2.1 Emergency exposure limits apply oni, to Duquesne Light and contractor personnel who are qualified as radiation workers at the Beaver Valley Power Station and have been issued BVPS dosimetry.

2.2 The establishment of these emergency exposure controls in no manner suggests that the exposures are acceptable. Although 10 CFR 50.47(b)(11) requires that the EPP contain emergency expostire control measures, any exposure greater than 10 CFR 20 provisions is reportable to the NRC.

3.0 CRITERIA Defmitions 3.1 3.1.1 Accident Exoosure: Exposure to radiation or radioactive materials that results from an unexpected event. Accident exposure refers to the immediate consequences of the unexpected event and the immediate corrective / mitigative actions of personnel present at the scene when the event occurred. Accident exposures are not controlled by the Health Physics Manual (HPM) or the Emergency Preparedness Plan (EPP), but may be reportable to the NRC under 10 CFR 20 and/or 10 CFR 50.72.

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l EMERGENCY EXPOSURE CRITERIA AND CONTROL .

l 3.1.2 Emergencv Exoosure: Exposure to radiation or radioactive materials that is the result of actions taken in response to an emergency condition classified and declared pursuant to the

! BVPS Emergency Preparedness Plan. Emergency exposure refers to radiation exposure caused by those assessment, corrective, and mitigative actions that are required on an immediate basis to save human lives, or to prevent or minimize the collective exposure of large populations. Such activities are directed by the Control Room or by the TSC/ EOF. Planned Special Exposures (see 3.1.4) are not considered emergency exposurcs.

l 3.1.3 Life Savine Action: Those actions related to the search and rescue of injured persons.

, 3.1.4 Planned Special Exposure (PSD: As defined in 10 CFR 20, an I ;, infrequent exposure to radiation, separate from and in addition to the annual dose limits. The HPM delineates requirements to be met in classifying an exposure as a PSE. PSEs might be warranted in the recovery phase. However, it is unlikely that the PSE requirements could be met during the initial phases of the emergency.

3.2 All emergency exposure extensions are subject to the .following conditions:

3.2.1 All exposures shall be maintained such that the TEDE is as low.

as reasonably achievable during emergencies, noting that it may

be necessary to tradeoff individual personal exposure against collective population exposure offsite, or in the interest of saving ,

human lives.

3.2.2 ' Emergency exposure limits apply only during emergencies declared pursuant to the rmergency Preparedness Plan.

3.2.3 The Emergency Director, with the advice of the Radiological Controls Coordinator, shall approve all emergency exposures in excess of 10 CFR 20 limits. This approval shall be documented.

However, the approval may be relayed verbally and documented later.

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EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL .

3.2.4 Emergency Exposure limits apply only to Duquesne Light and contractor personnel who are qtalified as radiation workers at the Beaver Valley Power Station and have been issued BVPS dosimeters.

3.2.5 Personnel who have received previous accident or emergency exposure in excess of 25 rem TEDE snall not participate ir.

further emergency exposure situations.

3.2.5.1 Since accident and emergency exposures are not required to be included in personnel exposure histories, it may be necessary to interview contractor and visitor personnel regarding such exposures.

3.2.6 Personnel who have declared pregnancy in accordance with the f HPM, shall not participate in emergency exposure situations.

1 3.2.7 With the exception of emergency exposures in excess of 25 rem TEDE, participation in emergency exposure situations need not be voluntary on the part of the individual emergency worker. j l

3.2.8 The dose of personnel authorized to receive emergency exposures I shall be monitored and recorded as provided in the Health Physics Manual.

• 3.3 Exposure Limitation l

3.3.1 Except as provided below, control of radiation exposures during an emergency shall be governed by the HPM.

3.3.2 The exposure of emergency response organization personnel should be maintained such that routine radiation exposure limits and administrative centrols contained within the HPM are met.

These routine exposure limits may be exceeded during the performance of emergency activities identified in paragraphs i 3.3.3 - 3.3.5, provided that the conditions of paragraph 3.2 are m et.

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EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL ,,

d 3.3.3 For activities performed on an immediate basis to prevent the failure of equipment necessary to protect the public health and safety, the TEDE of personnel directly involved shall not exceed 10 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with a lower dose '

consequence, are not readily available.

3.3.4 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prevent or mitigate a release of radioactivity to the environment for which offsite protective measures may be required, the TEDE of personnel directly involved shall not exceed 25 rem. This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available.

I 3.3.5 For activities necessary on an immediate basis (1) to save human life, (2) to restore equipment necessary to maintain critical safety functions or to establish and maintain a safe shutdown, or (3) to prevent or mitigate a release of radioactivity to the environment for which offsite protective measures may be required, the TEDE of personnel directly involved may exceed 25 rem, pmvided: 1 3.3.5.1 This limit is applicable only if actions establishing adequate or equivalent protection, with less dose, are not readily available, and, 3.3.5.2 Personnel assigned to these activities shall be volunteers, and, 3.3.5.3 Personnel assigned to these activities shall be briefed on, and understand, the risks associated with the estimated radiation exposure. For life saving activities, this briefing shall include' a discussion on the probability of a successful j rescue, and, I

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l EMERGENCY EXPOSURE CRITERIA AND CONTROL ,

3.3.5.4 Concurrence of the Company Chief Nuclear Officer, or designee, shall be obtained for any exposure projected to exceed 75 rem TEDE.

3.3.6 In addition to the TEDE limits established above, the dose equivalent to the lens of the eye shall be limited to three (3x) the limits specified in paragraph 3.3.3 a.._ '.3.4 above. The CDE to any organ (including the skin and body extremities) shall be limited to ten (10x) the limits specified in paragraph 3.3.3 and 3.3.4 above.

3.4 The internal exposure of BVPS emergency workers performing activities in the environment (i.e., outside plant buildings) is monitored and controlled as follows:

e 3.4.1 Monitoring of intemal exposure and assessment of CEDE may be

! waived for BVPS field monitoring team members under the following conditions:

3.4.1.1 The emergency involves a substantial core melt sequences with actual or potential early containment failure or bypass, and, 3.4.1.2 The release plume is present in the areas where the personnel are assigned, and, ,

3.4.1.3 An evacuation of the public has been ordered, but is incomplete, and, 3.4.1.4 The field monitoring team is assigned tasks out-of-doors associated with quantifying an unmonitored release from tM plant in support of decisions related to the need for extending protective measures, and, 6 Rev.7

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!l EPP/ Implementing Procedure EPP/IP 5.3 j EMERGENCY EXPOSURE CRITERIA AND CONTROL ,

3.4.1.5 If the DDE is likely to exceed 5 rem (i.e., assumes DDE to TEDE ratio of 5) for the duration of the exposure, personnel involved shall be volunteers, and, shall have been briefed on, and understand, the risks associated with the estimated radiation exposure and the uncertainty regarding the unmonitored CEDE, and,  !

3.4.1.6 If the DDE is likely to exceed 5 rem (i.e., assumes DDE to TEDE ratio of 5) potassium iodide shall be issued, and, 3.4.1.7 Conditions for emergency exposure delineated in paragraph 3.2 apply to these individuals.

j 3.4.2 Monitoring of internal exposure and assessment of CEDE of 1 emergency personnel workin; out-of-doors shall be accomplished by establishing rocket dosimeter administrative guides set at that  !

value of DDE that would ...aintain the sum of the DDE and CEDE below limits specified in paragraph 3.3. In addition:

3.4.2.1 These adjustments should be made using EDE to TEDE ratios determined from dose projections performed during the emergency using actual release source terms, if available. Ratios determined prior to the release from default source terms may be useful as bounding values.

3.4.2.2 These dosimeter administrative guides shall be f adjusted on the basis of actual field monitoring data, as these data become available, and, 3.4.'2.3 Conditions for emergency exposure delineated in paragraph 3.2 apply to these individuals.

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EMERGENCY EXPOSURE CRITERIA AND CONTROL ,

\

l 3.4.3 Monitoring of internal exposure and assessment of CEDE is not

( required if the release has not started, or if plume is no longer present, as this reduces the potential for uptake such that CEDE is negligible. In this case, emergency worker administrative guides are based on DDE.

i 3.5 Post-Exposure Evaluations 3.5.1 Personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance.

3.5.2 An exposure evaluation shall be performed to determine the individual dose. This dose may include assessment of the following dose quantities as applicable to the exposure situation:

i SDE, DE, DDE, ALI, CDE, CEDE, and TEDE. This evaluation should be based on observed area dose rates, airborne activity measurements, and dosimetry results. This evaluation

{

shall be documented in an appropriate format and filed with the j individual's exposure records. Appropriate reports shall be submitted to the Onsite Safety Committee and the USNRC. .

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3.5.3 If an individual's external dose exceeds 10 rem DDIE, 30 rem '

dose equivalent to the lens of eye, and/or 100 rem dose equivalent skin or an extremity, the details of the exposure incident shall be brought to the attention of a physician. The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations.

3.5.4 If an individual's external dose exceeds 25 rem DDE,150 rem l dose equivalent to the lens of eye, and/or 250 rem dose equivalent skin or an extremity, the individual shall be examined by a physician. The physician shall determine the need, extent, l- and nature of any clinical, biological, or biochemical examinations, or necessary medical surveillance.

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L EPP/ Implementing Procedure EPP/IP 5.3 l EMERGENCY EXPOSURE CRITERIA AND CONTROL ,,.

i 3.5.5 If an individual's intake exceeds 1.0 ALI, the details of the exposure incident shall be brought to the attention of a physician.

The physician shall determine the need, extent, and nature of any clinical, biological, biochemical examinations, or necessary medical treatment.

E. FROCEDUR._E 1.0 In the event emergency exposure is necessary, the following actions should be parformed. Although it is preferable to perform and document these steps prior to the exposure, if necessary the Emergency Director may verbally authorize the increased exposure and complete the documentation at a later time.

1.1 Per Attachment 1, determine the appropriate Emergency Exposure i Authorization Limit.

(~ 1.2 Complete Section A of the Emergency Exposure Authorization Form I (Attachment 2). Line 6 of the form must be signed by the Emergency Director. 1 1.3 The individual to receive the increased exposure will complete Section  ;

B.

1.4 The individual will be briefed on the radiological and other coliditions in the area (or expected in the area), the tasks to be performed, ALARA measures applicable to the task, and contingency measures, prior to entry to the affected area. Included in this briefing shall be a discussion of the biological risks associated with the exposure to be incurred.

l.5 The individual performs the assigned tasks.

l.6 Following the exposure, the Radiological Controls Coordinator, or designee, will complete and sign Section C and D of the Emergency Exposure Authorization Form.

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I EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND CONTROL F. FINAL CONDITIONS This procedure will be terminated when all sections of Attachment 1, " Emergency Exposure Authorization Form" have been completed and/or assignments are made for necessary exposure reports. The original of Attachment I should be filed in the individual's personnel exposure history records and a copy sent to the Manager, EPP for inclusion in event records.

1 G. ATTACHMENTS .

i 1.0 Emergency Exposure Authorization Limits 1

2.0 Emergency Exposure Authorization Form f.

i f

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l EPP/ Implementing Procedure EPP/IP 5.3 EMERGENCY EXPOSURE CRITERIA AND COS"rROL ATTACHMENT 1 (1 of 1) ,

EMERGENCY EXPOSURE AUTHORIZATION LIMITS Control radiation

exposures per Health l Physics Manual ,

Declared Emergoney AND Personnel are qualified N radiation workers at -

BVPS AND 3 No declared pregnant Y ,

Control radiation

exposures per Health l Physics Manual Exposure necessary t prevent failure of N

equipment necessary for -

the protection of :he pubfc Y a Limit exposure to: l 4 l . 10 rem TEDE

'* " 30 rem iens of eye Exposure necessary to: 100 rem organ CDE (1) save human life N OR (2) mitigate radioactive releases comparable to ~~

EPA PAGs OR (3) restore plant .

equipment necessary Y ,

for rnaintaining Critical Safety Functions Limit exposure to:

. 25 rem TEDE g 75 rem lens of eye

" 250 rem organ CDE Personnet are volunteers and have N

been briefed on risks of -

projected radiation exposure Limit exposure to:

75 rem TEDE l 225 rem lens of eye v I 750 rem organ CDE Duquesne Light Chief N Nuclear Ofreer -

authorization for exposure >75 rem y l  : No upper limit 11 Rev.7 l

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_( i EMERGENCY EXPOSURE CRITERIA AND CONTROL ,

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PP/ Implementing Procedure EPP/IP 5.3 I

A5.715G EMERGENCY EXPOSURE CRITERIA AND CONTROL ,

ATTACIIMENT 2 (1 of 3) .

EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION A

1. Name (to receive exposure):

Soc. Sec. No.:

2. Individual Badge Number: Employer /DLC Dept.; ,

3. Task (s) to be Performed:

4 Date of Authorization: Authorized Limit:

5. Conditions:

_ Individual is a volunteer or professional rescue person for exposure > 25 rem.

_ Individual is broadly familiar with radiological consequences of exposure.

_ Individual has not declared pregnancy.

_ Individual has not received a previous emergency exposure in '

excess of 25 rem TEDE.

__. Dose rates in area known/ measurable.

_ Life Saving Action?

_ Corrective action that will nrevent failure of equipment necessary for public -

health & safety?

_ Corrective action that will restore equipment necessary for maintaining critical safety functions?

6. Emergency Director: Date:

(Signature) j i

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EPP/ Implementing Procedure EPP/IP 5.3 k '

A5.715G .

EMERGENCY EXPOSURE CRITERIA AND CONTROL

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A'ITACHMENT 2 (2 of 3) .

EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION B I have been briefed in the radiological consequences of the proposed emergency exposure, and I have volunteered to perform the emergency measures during which I will receive the emergency exposure.

7. Signature: Date: .

SECTION C (Attach Exposure and Medical Evaluations)

1. Dose equivalent assigned for entry:

2.

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2. TLD/ Dosimeter Results:

3. Bioassay Results:

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4. Medical Evaluation / Action:

Doctor

5. Radiological Control Coordinator: Date:

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A5.715G EMERGENCY EXPOSURE CRITERIA AND CONTROL

ATTACHMENT 2 (3 of 3) .

l l EMERGENCY EXPOSURE AUTHORIZATION FORM i

SECTION D

1. Disposition (Allow additional exposure, restricted access, etc.)

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RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual

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OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training l

l SUBDIVISION: On-the-Job Training I

f l OJT CHECKLIST /JPM TITLE: Classify an Emergency L JPM NO.: WD-ADM3 (Scenario 1) l COMPUTER CODE: N/A l

Revision No. Date Revision No. Date l

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I PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Classify an Emergency Revision Approval No. Brief Description Revised by: Signature Date Revision 9

l BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET t

JPM Number: WD-ADM3 (Scenario 1) Rev: System #: Faulted:

JPM

Title:

Classify an Emergency K/A

Reference:

2.4.40 [4.0) Task ID #: )

JPM Designation: NO [] RO X SRO JPM Application: X NRC X Initial Exam Training Evaluation Method LOCATION TYPE Perform [3 Plant Site [3 Training ,

i X Simulate X Simulator [3 Annual Requal. Exam Classroom [3 OJT X Initial Operator Exam 1 Administered By: [3 Other: l l

BV-T NRC l Other:

Evaluation Results I Performer: Name: Employee No:

Results SAT Time (minutes)

UNSAT* Allotted: 20 Actual: l Time Critical: Yes X No

• Comments (Required for UNSAT Evaluation): l Evaluation Results Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT' Question #1 N/A 71oyee No:

Question #1 N/A []

Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL #AS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET o

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task- lClassifyanEmergency INITIAL The conditions that have occurred during the scenario.

CONDITIONS:

INIT. CUE: Determine the Emergency Classification.

1 At this time, ask the evaluator any questions you have on-this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM". ,

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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RIL CA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE

EVALUATOR DIRECTION SHEET JPM NUMBER

WD-ADM3 (Scenario 1)

JPM TITLE: Classify an Emergency RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Classify an Emergency INIT. CONDITIONS: The conditions that have occurred during the scenario.

TASK STAN.: Select the correct Emergency Classification level.

[ INIT. CUE: Determine the Emergency Classification.

REFERENCES:

EPP/I-la, Revision 6 TOOLS: None HANDOUT: EPP/I-la, Revision 6 l

l L

i j

l Revision 9 l

l \

L____-_______________._

RTL #AS.635.J f NUMBER- TITLE WD-ADM3 Classify An Emergency STEP STANDARD l (Indicate "S" for Sat. or "U"

("C" dencces critical step) for Unsat.;

START TIME:

1. Reviews plant conditions 1.1 Review plant conditions.

Comments:

2. Identify applicable 2.1 Identify Criterion 1.2.4 Criterion and Indicators as applicable.

Comments:

3.C Determine applicable 3.C Identifies the Emergency Classification. classification as an Alert.

Comments:

i STOP TIME i

l' Revision 9 E 2 _ -- - __-- _ ___ . _ _ _

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify an Emergency JPM NO.: WD-ADM3 (Scenario 2)

COMPUTER CODE: N/A Revision No. Date Revision No. Date i

PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

l Director, Operations Training, i- or Designee 1

i Revision 9 i

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual 4

LESSON PLAN AND OJT REVISION APPROVAL SHEET l

DOCUMENT TITLE: Classify an Emergency I

i l Revision Approval No. Brief Description Revised by: Signature Date l

r i

l J I I l

i i

L i

ll t

Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET e

JPM Number: WD-ADM3 (Scenario 2) Rev: System #: Faulted: 1 JPM

Title:

Classify an Emergency K/A

Reference:

2.4.40 [4.0) Task ID #:

JPM Designation: [3 NO RO X SRO JPM' Application: US NPC X Initial Exam Training Evaluation Method LOCATION TYPE Perform [3 Plant Site Training X Simulate X Simulator Annual Requal. Exam l

Classroom OJT X Initial Operator Exam Administered By: Other:

[] BV-T NRC I

Other-l i

Evaluation Results Performer: Name: Employee No:

Results [3 SAT Time (minutes)

UNSAT* Allotted: 20 Actual:

Time Critical: Yes X NO

• Comments (Required for UNSAT Evaluation):

Evaluation Results [3 Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 N/A []

Employee No:

Question #1 N/A Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9 i

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l

CANDIDATE DIRECTION SHEET 4

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

l Task, Classify an Emergency i

l INITIAL The conditions that have occurred during the scenario.

CONDITIONS:

INIT. CUE: Determine the Emergency Classification.

4 At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM". ,

1 Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evalua;or, l

l Revision 9 l

RTL CAS.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE i EVALUATOR DIRECTION SHEET JPM NUMBER: WD-ADM3 (Scenario 2)

JPM TITLE: Classify an Emergency RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Classify an Emergency INIT. CONDITIONS: The conditions that have occurred during the scenario.

TASK STAN.: Select the correct Emergency Classification level.

INIT. CUE: Determine the Emergency Classification.

REFERENCES:

EPP/I-3a, Revision 6 TOOLS: None HANDOUT: EPP/I-la, Revision 6 l

i Revision 9

)

i RTL #A5.635.J 1

1 NUMBER TITLE l

WD-ADM3 Classify An Emergency l l

4 STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

START TIME: l l

1. Reviews plant conditions 1.1 Review plant conditions.

i l

Comments: i l

1

2. Identify applicable 2.1 Identify Criterion 1.2.3 Criterion and Indicators and 3.1 as applicable.

Comments:

3.C Determine applicable 3.C Identifies the Emergency Classification. classification as a Site Area Emergency.

Note: It is expected that the Comments:

scenario will result in both 1AE and 1DF being deenergized for more than l 15 minutes. If 1AE is l returned within 15 minutes the classification may change.

STOP TIME

( Revision 9 f

L--___---_-----

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division

, Training Administrative Manual

(

OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Classify an Emergency JPM NO.: WD-ADM3 (Scenario 3)

COMPUTER CODE: N/A Revision No. Date Revision No. Date PREPARED BY: DATE:

i APPROVED.FOR

( IMPLEMENTATION: DATE:

l Director, Operations Training, ,

or Designee l

l Revision 9

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Classify an Emergency Revision Approval No. Brief Description Revised by: Signature Date l

i I

l e

l l

Revision 9 L_____-_____-_______________________________--_-___-____--------------------------------------------------------------------------

l BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: WD-ADM3 (Scenario 3) Rev: System #: Faulted: O i JPM

Title:

Classify an Emergency K/A

Reference:

2.4.40 [4.0] Task ID #:

l JPM Designation: [] NO RO X SRO l JPM Application: X NRC X Initial Exam Training I i

Evaluation Method LOCATION TYPE

[3 Perform Plant Site Training X Simulate X Simulator Annual Requal. Exam I Classroom [] OJT X Initial Operator Exam Administered By: Other:

BV-T NRC Other:

t .

Evaluation Results Performer: Name: Employee No:

Results SAT Time (minutes)

[] UNSAT* Allotted: 20 Actual:

Time Critical: [] Yes x No l

• Comments (Required for UNSAT Evaluation):

Evaluation Results Check here if same as above Observer 1: Name: Employee No:

! Observer 2: Name Employee No:

l Observer 3: Name Employee No:

! Observer 4: Name Employee No:

Time (minutes) Results i

Question ID Allotted Actual SAT UNSAT*

Question #1 N/A Employee No:

Question #1 N/A Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9 r

RTL CA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l 1

CANDIDATE DIRECTION SHEET 1

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Classify an Emergency Taska l

( INITIAL The conditions that have occurred during the scenario.

r CONDITIONS:

l l INIT. CUE: Determine the Emergency Classification.

l l

\

I l At this time, ask the evaluator any questions you have on this JPM.

f. When satisfied that you understand the assigned task, announce j "I am now beginning the JPM". .

Simulate performance or perform as directed the required task.

Point to any indicator or component you verify or check and I announce your observations.

After determinir.g the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

I l

1 l

Revision 9 i

w_ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ .______________________________-___________-_____a

i l

RIL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE l I

i

EVALUATOR DIRECTION SHEET  ;

4 JPM NUMBER: WD-ADM3 (Scenario 3) l l

JPM TITLE: Classify an Emergency l

RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Classify an Emergency INIT. CONDITIONS: The conditions that have occurred during the scenario.

TASK STAN.: Select the correct Emerger.cy Classification level.

INIT. CUE: Determine the Emergency Classification.

REFERENCES:

EPP/I-la, Revision 6 l

l i

TOOLS: None  ;

HANDOUT: EPP/I-la, Revision 6 l

Revision 9 l

L

RTL #AS.635.J

~

! NUMBER TITLE WD-ADM3 Classify An Emergency STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

START TIME:

1. Reviews plant conditions 1.1 Review plant conditions.

Comments:

2. Identify applicable 2.1 Identify Criterion 1.1.1 l Criterion and Indicators and 1.2.1 as applicable.  !

J Comments:

l 3.C Determine applicable 3.C Identifies the Emergency Classification. classification as a Site Area Emergency.

Note: It is expected that the Comments:

l scenario will result in l both 1AE and IDF being

, deenergized for more than

! 15 minutes. If-1AE is returned within 15 minutes the classification may change.

STOP TIME Revision 9

l l

RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division

, Training Administrative Manual i

OJT CHECKLIST /JPM COVER PAGE PROGRAM TITLE: Licensed' Operator Training SUBDIVISION: On-the-Job Training

! OJT CHECKLIST /JPM TITLE: Classify an Emergency l JPM NO.: WD-ADM3 (Scenario 4) l COMPUTER CODE: N/A Revision No. Date Revision No. Date i

t i

i l

! PREPARED BY: DATE:

APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision 9

RTL #AS.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual j I

LESSON PI AN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Classify an Emergency Revision Approval No. Brief Description Revised by: Signature Date 1

I e

l l

l l

l Revision 9 l

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET k JPM Number: WD-ADM3 (Scenario 4 ) Re : System 6: Faulted:

JPM

Title:

Classify an Emergency K/A

Reference:

2.4.40 (4.0] Task ID #:

JPM Designation: NO RO X SRO JPM Application: X NRC X Initial Exam Training Evaluation Method LOCATION TYPE l

Perform Plant Site [] Training X Simulate X Simulator Annual Requal. Exam Classroom OJT X Initial Operator Exam Administered By: [] Other:

[] BV-T NRC Other:

Evaluation Results l- Performer: Name: Employee No:

l Results [3 SAT Time (minutes)

UNSAT* Allotted: 20 Actual:

Time Critical: Yes X No

• Comments (Required for UNSAT Evaluation):

F Evaluation Results Check here if same as above Observer 1: Name: Employee No:

Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

l Question #1 N/A Employee No:

Question #1 N/A Employee No:

• Comments (Required for UNSAT Evaluation)-  !

t Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9 l

l 4

l RTL*#A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET t  ;

THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task, Classify an Emergency >

INITIAL The conditions that have occur 1.ed during the scenario.

CONDITIONS:

l l

2 INIT. CUE: Determine the Emergency Classification. l l

l i

l At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM". ,

Simulate performance or perform as directed the required task. 1 Point to any indicatar or component you verify or check and 1 announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the  ;

evaluator.  :,,

l 4

I l l

Revision 9 L___.____ _ _ _ _ . ._ _ . _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ . _ _ _ . . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _-

RTL CA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE 1

EVALUATOR DIRECTION SHEET

{ )

JPM NUMBER: WD-ADM3 (Scenario 4)

JPM TITLE: Classify an Emergency RECOMMENDED Simulator STARTING LOCATION:

DIRECTIONS: Classify an Emergency 1

INIT. CONDITIONS: The conditions that have occurred during l the scenario.

TASK STAN.: Select the correct Emergency Classification ,

1 level.

[ INIT. CUE: Determine the Emergency Classification.

REFERENCES:

EPP/I-la, Revision 6 TOOLS: None ,

HANDOUT: EPP/I-la, Revision 6 i

i l

Revision 9

RTL .fA5.635.J i NUMBER TITLE t

WD-ADM3 Classify An Emergency I

l-

! STEP STANDARD (Indicate "S" for Sat. or "U" l ("C" denotes critical step) for Unsat.)

l START TIME:

l l

l

1. Reviews plant conditions. 1.1 Review plant conditions.

i

! Comments:

l

2. , Identify. applicable 2.1 Identify Criterion 2.3 as Criterion and Indicators. applicable.

l Comments:

l

! 3.C Determine applicable 3.C Identifies the Emergency Classification. classification as a Site Area Emergency.

Note: It is expected that the Comments: l l scenario will result in I both 1AE and 1DF being

! deenergized for more than 15 minutes. If 1AE is returned within 15 minutes the classification may change.

STOP TIME Revision 9

Wi.'

., .i , . . , . _ . . ib EPP/ implementing Precedura EPP/l-1a R:cagnitlan e.nd CI:ssificatisn of Emerg!ncy Conditions Unit 1 A. PURPOSE i

1.0 This procedure describes the immediate actions to be taken to recognize and classify an emergency condition.

2.0 This procedure identifies the four emergency classifications and emergency action levels.

3.0 Reporting requirements for non-emergency abnormal events are provided.

B. REFERENCES 1.0 Beaver Valley Power Station Emergency Preparedness Plan and implementing Procedures.

2.0 Title 10, Code of Federal Regulations Part 50, Appendin E.

3.0 NUREG-0654/ FEMA-REP 1, Qiteria for Preparation and Evaluation of Radiological Emeraency Resoonse Plans and Preparedness in Suncort of Nuclear Power Plants l 4.0 Beaver Valley Power Station Operating Manual 5.0 NUMARC/NESP-007, Methodoloav for Development of Emeroency Action Levels

> C. RESPONSIBILITY The Emergency Director (Shift Supervisor, until properly relieved by a designated alternate) has the responsibility and authority for the performance of the actions prescribed j in this procedure.

D. ' ACTION LEVELS / PRECAUTIONS /GylDANCE 1.0 ACTION LEVELS 1.1 An off-normal event has occurred.

.1 1.2 An action step in a plant operating or emergency operating procedure refers to this procedure for classification of the indicated plant condition.

l 2.0 PRECAUTIONS l 1

l 2.1 The Emergency Director must review all applicable EALs to ensure that the  !

event is properly classified since a given INDICATOR may be associated with )

more than one CRITERION. A particular INDICATOR omitted from the fission product barrier matrix may be addressed as an event-based EAL in l

one of the other tabs. Event-based EALs may escalate to the fission product j l

l WMEPP11A DOC Revision 6 1

I

l l

l EPP/ implementing Prceduro EPP/l 1a  !

l Rec 2gniti:n cnd Classification of Emerg:ncy Canditi:ns Unit 1 l, barrier matrix. The Emergency Director may need to consider related events lt (e.g., fire and explosion) or the possible consequences of the event (e.g., fire in an MC" asulting in loss of AC)in classifying an event.

I

, 2.2 Continued surveillance and assessment of plant conditions are necessary to l ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.

l 2.3 If there is any doubt with regard to assessment of a particular EAL, the EAL i

Basis Document (i.e., Chapter 4 of the EPP) entry for that EAL can be re-viewed. Classifications shall be consistent with the fundamental definitions of the four emergency classifications (tabulated in Tab 4.7).

2.4 The Emergency Director shall take whatever mitigative or restoration actions are necessary to protect public health and safety. The Emergency Qirector shall not reject courses of action solely on the basis that the action would l result in escalation of the emergency classification.

3.0 GUIDANCE I

( 3.1 Structure of the EALs l 3.1.1 There are two types of Emergency Action Levels included in this

\g procedure:

3.1.1.1 Barrier-Based EAls: These EALs address conditions that represent potentiallosses, orlosses, of one or more of the Fuel Clad, RCS, or Containment fission product barriers.

!NDICATORs of these conditions include CRITICAL SAFETY FUNCTION status, fundamental indications such as subcooling or reactor vessel water level, or auxiliary

[ indications such as containment radiation monitor readings.

! Classifications are based on the number of barriers lost or potentially lost.

3.1.1.2 Event-Based EALs: These EALs address discrete conditions

! or events that are generally precursors to fission product barrier degradation, or are otherwise degradations in the level of safety of the plant. Events may be external (e.g., severe weather, earthquakes, loss of offsite power) internal (e.g.,

fires, explosions, instrumentation failure) or may involve radioactivity releases.

warenaooc Revision 6 2

I L a

l EPP/Impi:menting Prccedura EPP/l-1a R:c2gniticn Cnd Cl;ssific"ti n of Emerg:ncy C:nditi:n2 Unit 1 t

' i 3.1.2 The EALs are grouped by recognition category as follows:

! Tab 1 Fission Product Barrier Matrix Tab 2 System Degradation Tab 3 Loss of Power Tab 4 Hazards and ED Judgement Tab 5 Destructive Phenomena Tab 6 Shutdown Systems Degradation Tab 7 Radiological l

3.1.3 Each of the EAL tabs includes one or more columns that address one  !

initiating condition (e.g., fires). Each column provides EALs for each of

{

i the four emergency classifications, as applicable. A notation adjacent to each EAL identifies the plant operating mode (s) for which the EAL is applicable.

3.1.4 Each EAL is comprised of a CRITERlON, printed in bold type, and one or more INDICATORS. The purpose of each is as follows:

3.1.4.1 CRITERION: identifies the emergency condition and any numeric values which define that condition (i.e., the basis of lj -

the declaration) All classifications are based on an 4

assessment (i.e., determination that the condition is VALID)

by the Emergency Director that the CRITERlON has been met l or exceeded. Implicit in this protocol is the necessity for these assessments to be completed within 15 minutes (unless otherwise noted) from recognition of the INDICATOR.

3.1.4.2 INDICATOR: a specific instrumentation reading, a physical condition, a report by plant personnel, or other evidence that the associated CRITERION may be met. Upon recognition of one or more INDICATORS, the Emergency Director performs an assessment against the CRITERlON. Depending on the 4 particular condition, this assessment may be as simple as a review of the CRITERION, an instrument channel check, or a detailed calculation as in the case c. a radioactivity release.

l Implicit in this protocolis the necessity for these assessments l to be completed within 15 minutes (unless otherwise noted) l from the recognition of the INDICATOR.

3.1.4.3 The INDICATORS were selected with the objective of providing unambiguous guidance to assist with assessment of the CRITERION. There may be other INDICATORS not envisioned by the writers of this procedure that, in the judgment of the Emergency Director, correspond to the wxtreita ooc Revision 6 3

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EPP/ Implementing Preceduro EPP/l-1a R:c*gnitlen cnd Classification cf Emergrncy C nditions Unit 1 4

CRITERlON. In these cases, the Emergency Director should base the declaration on engineering judgment, using the supplied INDICATORS as examples of the severity of the condition.

3.2 Common Plant Conditions 3.2.1 IE an event occurs such that both reactor units are affected, e.g.,

tornado, toxic gas offsite, etc.,IBER the senior Nuclear Shift l

i Supervisor shall make the appropriate classification and assume the role of Emergency Director.

3.2.2 1E the common plant condition results in a higher emergency classification at one reactor unit, THEN the Nuclear Shift Supervisor from that unit shall make the appropriate classification and assume the role of Emergency Director.

3.3 Mode Applicability i

3.3.1 The plant operating mode that existed at the tima that the event occurred, prior to any protective system or operator action initiated in response to the condition,is compared to the mode applicability of the

, EALs.

!\

3.3.2 1E an event occurs, and a lower or higher plant operating mode is reached before the classification can be made . TEEN the classification shall be based on the mode that existed at the time that the event occurred.

3.3.3 The fission product barrier matrix is applicable oNy to those events that occur at mode 4 or higher. An event that is recognized in modes -

5 or 6 shall not be classified using the fission product barrier matrix, even if mode 4 is entered due to subsequent heatup. In these cases, Tab 6, Shutdown Systems Degradation, shall be used for classification.

3.4 Transient Events

-3.4.1 For some EAls the existence of the event, without regard to duration, is sufficient to warrant classification. In these cases, the appropriate emergency classification is declared as soon as the Emergency l

Director assessment concludes that the CRITERION is met.

3.4.2 Some EAls specify a duration of occurrence. For these EALs the classification is made when Emergency Director assessment concludes that the specified duration is exceeded or will be exceeded wn m uooc Revision 6 4

I

EPP/Impl:menting Prcc: dura EPP/l 1a R:c:gniti:n cnd CI:ssificallEn cf Emerg ncy C;nditi:ns Unit 1 (l.e., condition can not be reasonably rectified before the duration elapses), whichever is sooner.

3.4.3 E a plant condition meeting an EAL CRITERlON is rectified before the specified duration time is exceeded, THEN the event is NQI classified by that EAL. Lower severity EALs, if any, shall be reviewed for possible applicability in these cases.

3.4.4 E a plant condition meeting an EAL CRITERION is HQI recognized at the time of occurrence, but is identified well after the condition has occurred (e.g., as a result of routine log or record review) AMQ the condition no longer exists, THEN an emergency shall NQI be declared. .However, reporting under 10 CFR 50.72 may be required.

Such a condition could occur, for example, if a followup evaluation of an abnormal condition uncovers evidence that the condition was more severe than earlier believed.

3.4.5 IF an emergency classification was warranted, but the plant condition has been rectified (such that the CRITERION is no longer met) prior to declaration and notification, THEN the following guidance applies:

3.4.5.1 For transient events that would have been declared as i

UNUSUAL EVENTS, no emergency is declared. However, the event shall be reported to those local, state, and Federal agencies designated to receive the initial notification form.

These agencies shall be told that the UNUSUAL EVENT condition was rectified upon detection and no emergency is being declared. ,

3.4.5 ^ For transient events that would have been declared as an ALERT, SITE AREA EMERGENCY, or GENEFiAL EMERGENCY, the event shall be declared and the emergency response organization activated. The EAL CRITERIA for these events has been set at a threshold that warrants declaration even if the initiating condition has been rectified. Termination can occur when the criteria of EPP/IP-6.2, Termination of the Emergency and Recovery can be satisified.

3.5 Declaration Timing and Assessment j Emergency conditions shall be classified as soon as the Emergency Director assessment of the INDICATORS shows that the CRITERlON is met. E the EAL ,pecifies a duration, THEN the event shall be declared as soon as it is dete mined that the condition cannot be corrected within the specified period.

WXEPP11 A DOC Revision 6 1

EPP/Impl:rnenting Prccedure Rec:gniti:n cnd Classification of Emergency Ccnditi:ns EPP/l-10 Unit 1 In either case, the assessment time starts from the point of recogtiition or

( report of one or more INDICATORS.

3.5.1 The assessment time is limited to 15 minutes, except as follows:

3.5.1.1 E the EAL specifies a duration (e.g., release exceeds 2x T/S for one hout), THEN the assessment time runs concurrently

\ with the required duration AND is the same length (e.g., in this example, one hour).

l 3.5.12 The assessment time and any required duration are NQI additive.

3.5.1.3 E the required duration is exceeded. .QB is unknown, when the condition is reported or recognized THEN the assessment -

time shall be limited to 15 minutes from the time of I recognition.

3.5.2 E the assessment cannot be completed within the specified period, THEN the event must be declared on the basis of INDICATORS th cannot be reasonably discounted.

, 3.6 Bases

(

3.6.1 1 Chapter 4 of the BVPS EPP provides the bases for these EALs. The I l bases can be used for guidance to assist the Emergency Director in classifying events for which the classification is not immediately

( apparent.

3.7 Defined Terms j

3.7.1 in the EALs, words written in uppercaso letters are defined terms i

having specific meanings as they relate to this procedure. Definitions of these terms are provided on the reverse side of most pages in the EAL section of this procedure. Such terms shall be interpreted as provided in the definitions. .

I

E. PROCEDURE  !

i 1.0 DETERMINE OPERATING MODE THAT EXISTED AT THE TIME THAT TH EVENT OCCURRED PRIOR TO ANY PROTECTION SYSTEM OR OPERATO ACTION INITIATED IN RESPONSE TO THE EVENT.

2.0 DETERMlNE IF THE CONDITION AFFECTS FISSION PRODUCT BARRIER AND, IF SO, PROCEED TO TAB 1.

WXEPPl1A DOC Revision 6 6 '

l EPP/impl:menting Prccedur0; i EPP/l-10 R:c:gniti:n cnd Classificati:n cf Emergency Canditi:ns Unit 1 2.1 E the condition involves any of the following M the initial mode was 1-4

!l THEN proceed to Tab 1 and follow instructions provided M continue with Step 2.2.

2.1.1 CSF status tree ORANGE PATH or RED PATH conditions 2.1.2 Core exit thermocouple readings above 700 F 2.1.3 Reactor vessel full range water level less than 39% (no RCPs) 2.1.4 Elevated RCS activity >300 pCi/gm 2.1.5 Elevated Containment High Range Area Radiation Monitor reading 2.1.6 RCS leakrate large enough to require a 2nd charging pump 2.1.7 Loss of RCS subcooling 2.1.8 Steam Generator Tube Rupture 2.1.9 Containment bypass or loss of integrity 2.1.10 aise in containment pressure or hydrogen concentration 2.2 Consider other related event-based EALs. E other EALs are applicable, l THEN perform Steps 3.0 and 4.0 if necessary. Otherwise, go to Step 5.0 l 3.0 CATEGORIZE THE EVENT INTO ONE OF THE INITIATING CONDITIONS AND LOCATE THE TAB.

3.1 Locate one of the EAL indices provided at the start of each tab.

f k

3.2 Review the index to identify the tab that addresses the event that has occurred.

3.3 Turn to the appropriate tab.

NOTE The assessment of an emergency condition shall be completed as soon as possible and within 15 minutes of the recognition of one or more INDICATORS. E the assessment cannot be completed within the specified period, THEN the event must be declared on the basis of INDICATORS that cannot be reasonably discounted.

NOTE E the EAL specifies a duration (e.g., release exceeds 2x T/S for one hour), THEN the assessment time runs concurrently with the required duration M is the same length. E the required duration is exceeded, .QB is unknown, when the condition is reported or recognized THEN the assessment time shall be limited to 15 minutes from the time of recognition.

4.0 ASSESS THE EVENT AND COMPARE TO THE EALS 4.1 Locate the EAL for the highest severity emergency classification that is applicable for the initiating condition and operating mode WEPPD A doc Revision 6 7

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EPP/Impi:monting Precedure EPP/l-1a R:c:gnitien cnd Clessificaticn of Emergency Canditlens Unit 1

, 4.2 Review the INDICATORS and CRITERION for that EAL l

4.3 E the specified INDICATORS are not observed, THEN:

4.3.1 Proceed to the next lower severity EAL and re-perform step 4.2 & 4.3.

4.3.2 E none of the EALs for an initiating condition are met, THEN re-perform steps 3.0 and 4.0 for related initiating conditions.

4.3.3 E the actions above do not identify an applicable EAL, . TEEN review the observed conditions against Tab 4.7, Hazards and Emergency Director Judgment.

4.3.4 E, after performing the above, no EAL is identified, THEN proceed to l step 6.0.

4.4 E the specified INDICATORS are observed. TBEN:

4.4.1 Perform necessary assessments to validate the instrument readings and/or confirm reported observations.

4.4.2 Initiate any sampling, inspections, or dose assessments specified by the EAL.

NOTE E the CRITERION specifies an event or condition duration, THEN the classification shall be made as soon as the duration is exceeded, .QB when it is apparent that the duration will be exceeded, whichever is earlier.

f l 4.4.3 Compare the results of the assessments to the CRITERION.

L i

NOTE  ;

A given INDICATOR may apply to more than one CRITERlON. The Emergency l Director shall review other related EALs for applicability.

4.5 E the assessment concludes that the CRITERlON is met, THEN the classification shall be made. Proceed to Step 5.0 4.6 E the assessment concludes that the CRITERlON is not met. .TBfB re-perform steps 3.0 and 4.0 for other related initiating conditions as applicable.

4.7 E no classification results from the above, THEN proceed to step 6.0.

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t WXEPPnA doc Revision 6 8

EPP/Impl:menting Prccedure EPP/1-1a R:ctgnitlen and CIIssification cf Emergency Canditions Unit 1 f

lI 1 NOTE The declaration of the emergency classification shall be made as soon as the Emergency '

} Director has a: .ssed that the EAL has been met.QB will be met, ANQ within 15 minutes of recognition of the INDICATOR. Once the emergency is classified, notifications to state and local governments shall be completed within 15 minutes of the declaration.

5.0 DECLARE THE EMERGENCY CLASSIFICATION AND TRANSITION TO l RESPONSE PROCEDURES l

l 5.1 E an UNUSUAL EVENT is declared,IHEN proceed to EPP/l-2 5.2 E an ALERT is declared. IliEN proceed to EPP/1-3 5.3 E a SITE AREA EMERGENCYis declared, THEN proceed to ERP/l 4 5.4 E a GENERAL EMERGENCY is declared, THEN proceed to EPP/l-5 l

NOTE The step below is implemented only if an emergency classification is NQI made. E a classification is made, THEN the transition indicated in step 5.0 should have been made.

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6.0 EVALUATE THE NEED FOR AND MAKE NON EMERGENCY NOTIFICATIONS 6.1 E the abnormal condition is reportable to the NRC pursuant to 10 CFR 50.72 and NPDAP 5.1,IldEN perform the following:

6.1.1 Complete the NRC Event Notification Form, Attachment 4 to EPP/IP-1.1.

6.1.2 Notify DLC Corporate Communications of the event per NPDAP 5.3 and provide the information on the NRC Event Notification Form.

i 6.2 E directed by station management, THEN make courtesy calls to the followir tate and local agencies on a timely basis consistent with normal working nours.

l 6.2.1 BCEMA j 6.2.2 PEMA 6.2.3 CCEMA 6.2.4 HCOES wappn, ooc Revision 6 9

EPP/Impirmenting Prce: dure EPP/l-1a l R:c:gnitisn cnd Classification cf Emergsncy Canditions Unit 1 lj F. ElHAL CONDITIONS 1.0 For emergency events, the transition to the appropriate response procedure has l

been made and actions pursuant to that procedure are in progress.

2.0 For non emergency events, required notifications have been completed, t G. ATTACHMENTS 1.0 Tabs for Classification of Emergency Conditions H. FIGURES 1.0 Figures are identified on the EAL Indices

)

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WXEPPD A DOC Revision 6 10 l

ES-301 Individual Walk-Through Test Outline Form-ES-301-2 Facility: Beaver Valley 1 Date of Examination: 4/20/98

( Examination Level: SRO-1 Operating Test Number: 1 System / JPM Title / Type Codes

• Safety Planned Followup Questions:

Function K/A/G - Imponance - Description I 1. CVCS/RWST Makeup I a. 2.1.24 //2.8'3.1// Flow path for procedure Using Blender b. 2.1.10 //2.7/3.9// Baron dilution TS D S l 2. ECCS/ Align S1 Pumps for 11 a. 2.4.18 //2.7/3.6'/ Purpose for 110t Leg Recirculation l Hot / Cold Leg Recirculation b. 2.1.10 //2.7/3.9// ECCS Flowpath Tech Spec l D S l 3. Pressure Control / Place the 111 a. 010 K6.01//2.7/3.1// Wide Range Pressure Fails Downscale l Overpressure Protection b. 2.1.12 //2.9/4.0!/ Restrictions on RCS pressure with an accumulator unisolated.

System in Service D S L

4. AFW/ Monitoring AFW IV a. 061 A202 //3.2/3.6// Other effects of a loss of air on AFW Pump Performance During b. 061 K408 //2.7/2.9// Normal Response of the Recirculation Valves Loss of Station Instrument Air l N S l 5. Control Room Evacuation Vill a. 068 A1.02 //4.2/4.5// Preferred AFW Pump

b. 068 Al.01//4.3/4.5// Inability to Operate Atmospheric Dump Valves D S A

! 6. IR/lRNIS N-36 Functional Vll a. 015 A2.02 //3.1/3.5// Overcompensation Effects l Test b. 015 A3.03 //3.9'3.9// Indication at NIS rack when at power l D S L

7. Containment Spray / V a. 026 Kl.02 //4.1/4.1// Normal alignment of cooling water Response to Containment b. 026 A2.04 //3.9/4.2!/ Cooling water from quench spray l Flooding (FR-Z.2) ,

l N S l l

8. AFW/ Response to Loss Of IV a. 061 Kl.07 //3.6'3.8'/ Service Water supply to AFW l AFW Pump Suction Flow b. 061 Kl.01//4.1/4.1// Leak in the AFW system 1 l

N P

9. DG/ Locally Start the No.1 VI a. 064 Kl.03 //3.6!4.0!/ Emergency stopping of the DG Emerg Diesel Generator b. 2.1.12 //2.9/4.0!/ DG Operability TS (Fuel Oil) i D P A l 10. ECCS/ Transfer to Cold Leg ill a. E03 EKl.2 //3.6/4.1//Effect oflow head SI pump miniflow.va e failing to l Recirculation (Local) close j b. 011 K3.12 //4.4/4/6// Reason for closing con-operating 1111S1 discharge vals es i

D P R Type Codes: (D) Direct from bank, (M)odified from bank, (N)ew, ( A)lternate Path, (C)ontrol Room, (S)imulator, (P)ls.nt, (L)ow Power, (R)CA l

NUREG-1021 Interim Res. 8, January 1997 File Name: JPM Outline _revi Date and Time Printed: 03/17/98 8:02 AM Prepared by WD Associates. Inc.

l N_-__________-_______-__________________

)

JPM Changes:

J

1. Place the Overpressure Protection System in Operation JPM - Changed second question from Normal Response to the Recirculation Valves to a failure of the suction flow transmitter and how that w ould affect operation of the pump. Both questions test similar concepts of how the recirculation valves operate. KA was not changed.

2. Control Room Evacuation JPM - Change first question from "Available Boration Methods" to

" Preferred AFW Pump" because conflicting information was identified in plant reference material.

~ KA was not changed.

3. Response of Loss of AFW Pump Suction Flow JPM - Changed second question because unable to develop a higher cognitive level question associated with required number of AFW pumps. Changed KA Number.

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RTL #A5.640E DUQUESNE LIGHT COMPANY Nuclear Power Division Training Administrative Manual 1

-OJT CHECKLIST /JPM COVER PAGE 1

PROGRAM TITLE: Licensed Operator Training SUBDIVISION: On-the-Job Training OJT CHECKLIST /JPM TITLE: Makeup to the Refueling Water Storage

. Tank JPM NO.: WD-CR1 N/A COMPUTER CODE:

Revision No. Date Revision No. Date l-

.l l

PREPARED BY: DATE:  !

I APPROVED FOR IMPLEMENTATION: DATE:

Director, Operations Training, or Designee Revision-9 l _ _ _ . _ __ _ . _ _ _ _ _ _ . _ _

l RTL #AS.640E DUQUESNE LIGHT COMPANY i Nuclear Power Division {

i Training Administrative Manual 1

1 LESSON PLAN AND OJT REVISION APPROVAL SHEET DOCUMENT TITLE: Makeup to the Refueling Water Storage Tank Revision Approval No. Brief Description Revised by: Signature Date J

Revision 9

BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR COVER SHEET JPM Number: WD-CRl Rev: 0 System #: 004 Faulted: 0 JPM

Title:

Makeup to the Refueling Water Storage Tank K/A

Reference:

2.1.23 [3. 9/4.0) Task ID # :

JPM Designation: NO RO X SRO JPM Application: x NRC X Initial Exam O Training Evaluation Method LOCATION TYPE X Perform [3 Plant Site [3 Training Simulate X Simulator Annual Requal. Exam Classroom OJT X Initial Operator Exam Administered By: Other:

BV-T E3 NRC Other:

~

Evaluation Results Performer: Name: Employee No:

Results SAT Time (minutes)

UNSAT* Allotted: 20 Actual:

Time Critical: Yes X No

• Comments (Required for UNSAT Evaluation):

Evaluation Results Check here if same as above Observer 1: Name: Employee No:

l Observer 2: Name Employee No:

Observer 3: Name Employee No:

Observer 4: Name Employee No:

Time (minutes) Results Question ID Allotted Actual SAT UNSAT*

Question #1 10 []

Employee No

Question #2 10 i

Employee No:

• Comments (Required for UNSAT Evaluation):

Evaluator (Print): Organization:

Evaluator Signature Date:

Revision 9

RTL CA5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE CANDIDATE DIRECTION SHEET I

• THIS SHEET TO BE GIVEN TO CANDIDATE

• Read:

Task, Restore Refueling Water Tank Level.

INITIAL REFUELING WATER STORAGE TANK BELOW NORM. LEVEL CONDITIONS: (A6-20) alarm has been received. Reactor Makeup is not required at this time. Boric Acid Storage Tank Concentration is 7200 ppm. RCS Boron concentration is ppm.

INIT. CUE: The ANSS has directed that a 1000 gallons be added to RWST to raise level using the normal blender.

Inform the ANSS when makeup has been initiated to the RWST.

At this time, ask the evaluator any questions you have on this JPM.

When satisfied that you understand the assigned task, announce "I am now beginning the JPM".

Simulate performance or perform as directed the required task. Point to any indicator or component you verify or check and announce your observations.

After determining the Task has been met, announce "I have completed the JPM". Then hand back this sheet to the evaluator.

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Revision 9

RTL #A5.635.J BEAVER VALLEY JOB PERFORMANCE MEASURE EVALUATOR DIRECTION SHEET JPM NUMBER:

JPM TITLE: MAKEUP TO THE REFUELING WATER STORAGE TANK RECOMMENDED Simulator l

STARTING LOCATION:

DIRECTIONS: Restore Refueling Water Tank Level.

INIT. CONDITIONS: REFUELING WATER STORAGE TANK BELOW NORM.

LEVEL (A6-20) alarm has been received.

Reactor Makeup is not required at this I time. Boric Acid Storage Tank Concentration is 7200 ppm. RCS Boron concentration is ppm. RWST concentration is 2000 ppm.

TASK STAN.: Flow is initiated to restore level in the RWST.

INIT. CUE: The ANSS has directed that a 1000 gallons be added to RWST to raise level using the normal blender. Inform the ANSS when makeup has been initiated to the RWST.

REFERENCES:

10M-7.4.0, Issue 3, Rev. 3 .

TOOLS: None HANDOUT: 10M-7.4.0 Narrative Log Sheet i

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Revision 9 t__

l RTL #A5.635.J I

I NUMBER TITLE WD-CR1 Makeup to the RWST j I

STEP STANDARD l (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

f Evaluator Setup: IC21 - Lower )

RWST level until REFUELING WATER STORAGE TANK BELOW NORM.

LEVEL (A6-20) is received.

START TIME:

i Applicant locates and reviews

! 10M.7.Q.

t N

EVALUATOR CUE: Provide applicant with a copy of

10M.7.Q.

! 1. Verify or place Mode 1.1 IMU verified in or placed Control Switch in STOP, to stop. l l Benchboard A l l

! Comments:

(:

2.C Place Makeup Mode Selector 2.1.C 43/MU placed to MAN.

Switch to MAN position, Benchboard A.

Comments:

Revision 9 l

w-__-_-__

RTL #A5.635.J l

NUMBER TITLE WD-CR1 Makeup to the RWST l

l l

STEP STANDARD (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

3. Verify Blender Outlet to 3.1 [FCV-1CH-113B] CLOSED l Chg Pumps FCV is closed. indication verified lit.

Comments:

1 1

4. Verify Blender Outlet to 4.1 [FCV-1CH-114B) CLOSED l VCT FCV is closed. indication is verified lit.

Comments:

1 Revision 9 c-__-_____-_-___-.

.RTL CA5.635.J l

V l4 NUMBER TITLE

! i l I i WD-CR1 Makeup to the RWST '

i.

I l

l STEP STANDARD l (Indicate "S" for Sat. or "U"

("C" denotes critical step) for Unsat.)

5.C Direct local operator line 5.1C Directs lineup of up-local valves. following valves:

[1CH-87] Blender to Refueling Cavity Isolation - OPEN,

[lCH-89] Blender to Refueling Cavity Isolation - OPEN,

[lPC-35] Filter.1 A to Refueling Cavity -

(. CLOSED,

[lPC-36] Filter 1 B to Refueling Cavity -

CLOSED,

[lPC-37] (LS) Refueling Cavity Supply Cnmt Isol - i CLOSED,

[lPC-47] RWST Return -

OPEN.

EXAMINER CUE: Lineup has been completed.

Comments: i