Text

TSTF-258, R.4, Changes to Section 5.0, Administrative Controls
	ML040620102
Person / Time
Site:	Wolf Creek
Issue date:	08/05/2002
From:	; Nuclear Energy Institute
To:	; Office of Nuclear Reactor Regulation
References
	NUREG-1430, NUREG-1431, NUREG-1432, NUREG-1433, NUREG-1434 TSTF-258, Rev 4
	Download: ML040620102 (62)
	v • d • e

(1VOG-I 18, Rev. 0)

TSTF-258, Rev. 4 Industry/TSTF Standard Technical Specification Change Traveler Changes to Section 5.0, Administrative Controls NUREGs Affected:

j 1430

[j 1431 3

1432 g

1433

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1434 Classification: 3) Improve Specifications RecommendedforCLIIP?:

(Unassigned)

Priority (Unassigned)

Simple or Complex Change:

(Unassigned)

Industry

Contact:

Wideman, Steve (316) 364-4037 stwidem@wcnoc.com This proposed traveler supersedes travelers TSTF-86 (rejected by NRC and TSTF accepted), TSTF-121, TSTF-167 (rejected by NRC) and WOG-l 08 (Action Item 147). This traveler is based on the recommendations (with some exceptions noted below) in the April 9,1997 letter from C. Grimes (NRC) to J. Davis (NEI). This traveler proposes the following changes:

I) Revise Administrative Control 5.2.2, Unit Staff, to delete item b, revises item e eliminating specific details for working hour limits, and revises item g to clarify the requirements for the Shift Technical Advisor function,

2) Inserts brackets around entire second sentence in 5.3.1 and adds 5.3.2, Unit StaffQualifications to retain elements required in TS by regulations,

3) Revises Section 5.5.4 to be consistent with the intent of 10 CFR 20

4) Revises Section 5.6.4 to be consistent with Generic Letter 97-04, and

5) Revises Section 5.7 in accordance with 10 CFR 20.1601(c)

See attached justification.

Revision History OG Revision 0 Revision Status: Closed Revision Proposed by: Wolf Creek Revision

Description:

Original Issue Owners Group Review Information Date Originated by OG:

20-Nov-97 Owners Group Comments (No Comments)

Owners Group Resolution:

Approved Date: 20-Nov-97 TSTF Review Information TSTF Received Date:

20-Nov-97 Date Distributed for Review 06-Jan-98 OG Review Completed: Ea BWOG 2 NVOG

] CEOG &5 BWROG TSTF Comments:

Look at CEOG change to titles, Make indicated changes, Add SR 3.0.3 to 5.5.4, Clearly indicate or annotate the differences of the proposed TSTF versus the 4/9/97 letter.

TSTF Resolution:

Approved Date: 05-Feb-98 NRC Review Information NRC Received Date:

NRC Comments:

19-Mar-98 05-Aug-02 Traveler Rev. 2. Copyright (C) 2002, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

(NVOG-1 18, Rev. 0)

TSTF-258, Rev. 4 OG Revision 0 Revision Status: Closed 4121/98 - Under NRC review.

6/11/98 -NRC Comments:

5.7.2d.2 and 5.7.2d.3(ii)

The proposed change is not acceptable for high radiation areas with dose rates in excess of I R/hr. The STS provides several options for licensees to use and provides adequate flexibility while still maintaining an adequate level of control over workers in high radiation areas. The proposed changes will reduce the level of control maintained by the TS.

5.7.1e and 5.7.2e The proposed change to "..when the knowledge of the dose rates must be made to the worker." is not accepted. The STS provides appropriate controls to ensure workers are adequately controlled and protected while working in high radiation areas. The STS allows time for the RP technician to evaluate the radiological hazard and brief the workers about the radiological conditions in the work area prior to the workers entering the high radiation area. The control is required to ensure that workers do not focus solely on the work to be performed but remain informed about radiological conditions. However, there has been alternate wording to the STS proposed by a licensee that was accepted by the staff in a licensee amendment. The approved alternate wording follows: "Except for individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination and knowledge does not require documentation prior to initial entry." This alternate wording may be proposed by licensees in lieu of the STS. However, the wording of the STS will remain as issued.

We agree with the comment in 5.7.2.a.1, however, we do not fully understand it since the proposed words are the same as the standard TS (perhaps the standard TS was missing the [ for the designated positions).

5.7.2a The proposed change to substitute the word "inadvertent" for "unauthorized" is not accepted. High radiation area controls are divided into distinct modes of control; areas below I R/hr where barricades are acceptable to prevent inadvertent entry and areas above 1 R/hr where the radiological [hazard] is significantly greater and thus requires the use of locked doors which are not only intended to prevent inadvertent but to ensure that unauthorized entry is prevented. The use of the word "unauthorized" is expressly used to denote the extra controls that are required for high radiation areas greater than 1 R/hr. Regulatory Guide 8.38 does discuss the use of physical barriers to prevent unauthorized entry. The word "unauthorized" will continue to be used.

5.7.2a.2 The comment is not accepted. The STS does not imply that an area would be locked so as to prevent personnel from exiting the area. The STS is designed to be very clear and literal. The NRC and the licensee will recognize that a locked door will be "unlocked" when workers enter or exit the area, and this action would not result in a NOV. The standard TS wording will not be changed.

5.7.2f The comment in not clear. The STS control is offered to licensees as a "relief' from 10 CFR Part 20. If a licensee has a special need; a custom TS can be proposed and justified for the staff's consideration. The standard TS wording will not be changed.

Final Resolution:

Superceded by Revision Final Resolution Date: 11-Jun-98 TSTF Revision 1 Revision Status: Closed Revision Proposed by: WOG 05-Aug-02 Traveler Rev. 2. Copyright (C) 2002. EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

(AVOG-l 18, Rev. 0)

TSTF-258, Rev. 4 TSTF Revision I Revision Status: Closed Revision

Description:

Revised to Address NRC Comments:

5.7.2d.2 and 5.7.2d.3(ii) - Commcnt accepted.

5.7.1c and 5.7.2e - Comment accepted, except did not incorporate the following sentence: "These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination and knowledge does not require documentation prior to initial entry." This information was considered to be of a level of detail below that normally included in the Administrative Controls.

5.7.2.a.1 - Brackets removed.

5.7.2a - Comment accepted.

5.7.2a.2 - Comment accepted.

5.7.2f - Information added to the justification to address comment.

TSTF Review Information TSTF Received Date:

22-Sep-98 Date Distributed for Review 23-Sep-98 OGReviewCompleted:

i BWVOG i WOG R CEOG i BWROG TSTF Comments:

(No Comments)

TSTF Resolution:

Approved Date: 23-Sep-98 NRC Review Information NRC Received Date:

25-Scp-98 Final Resolution:

Superceded by Revision TSTF Revision 2 Revision Status: Closed Revision Proposed by:

NRC Revision

Description:

Revised changes to 5.7.1e and 5.7.2e perNRC comments to include the sentences, "These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry."

TSTF Review Information TSTF Received Date:

26-Oct-98 Date Distributed for Rcvicw 26-Oct-98 OG Review Completed: 0 BWOG [

NVOG 0 CEOG 2 BWROG TSTF Comments:

(No Comments) 05-Aug-02 Traveler Rev. 2. Copyright (C) 2002. EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

(NVOG-1 18, Rev. 0)

TSTr-258, Rev. 4 (WOG1 1, Re.

0 TSF-25, Rv._

TSTF Revision 2 Revision Status: Closed TSTF Resolution:

Approved Date: 26-Oct-98 NRC Rcvicw Information NRC Received Date:

28-Oct-98 NRC Comments:

11112/98-Rad Protection Branch agrees with Rad Areas position ofTSTF-258. Human Factors Branch insists that a sentence requiring the Plant Manager approve overtime limits on a routine basis be reinstated in theTS requirement. B. Tjaderto setup a meeting for 12/16 or 12/17 to discuss and resolve.

12/16/98 - NRC requested revision.

Final Resolution:

Superceded by Revision TSTF Revision 3 Revision Status: Closed Revision Proposed by:

TSTF Revision

Description:

Revised changes to 5.2.2.c to address NRC concerns regarding independent review of procedures to ensure overtime limits are maintained. The deleted sentence is replaced with the statement "Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned." As used in this application, the term independent is to only ensure the review is performed by individual (s) different than the individual (s) actually authorizing the over time. As used in this application, the term "periodic frequency" shall be based on plant experience, outage frequencies, and other management review practices (i.e., more frequent reviews conducted during shutdown / refueling when a lot of overtime can be expected, versus less frequent reviews at RTP with little anticipated overtime during which the reviews would not exceed the quarterly frequency). While no changes were made to the pages, there was discussion of and agreement by the NRC and the Industry that the meaning of the term "designee" as it is used in this section permits the designee to either be a permanent position or a temporary position to satisfy the requirements.

TSTF Review Information TSTF Received Date:

17-Dec-98 Date Distributed for Review 17-Dec-98 OG Review Completed:

i BWOG ;

WOG i CEOG i

BWN'ROG TSTF Comments:

(No Comments)

TSTF Resolution:

Approved Date: 18-Dec-98 NRC Review Information NRC Received Date:

24-Dec-98 NRC Comments:

12/16/98 - TSTF / NRC meeting.

Final Resolution:

Superceded by Revision Final Resolution Date: 03-Feb-99 TSTF Revision 4 Revision Status: Active Next Action:

Revision Proposed by:

NRC 05-A ug-02 Traveler Rev. 2. Copyright (C) 2002, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

(WN'OG-1 18, Rev. 0)

TSTF-258, Rev. 4 TSTF Revision 4 Rcvision Status: Active Next Action:

Revision Dcscription:

Revision 4 revised the Revision Dcscription for Revision 3 to included a parenthetical explanation of the meaning of "periodic frequency" requested by the NRC. No other changes were made to the package.

TSTF Review Information TSTF Received Date:

20-Jan-99 Date Distributed for Review 09-Mar-99 OG Review Completed: Z BWOG D WOG 21 CEOG

]

BWVROG TSTF Comments:

(No Comments)

TSTF Resolution:

Approved Date: 09-Apr-99 NRC Review Information NRC Received Date:

28-Apr-99 NRC Comments:

6/16/99 - NRC stated they believed this change was approved.

Final Resolution:

NRC Approves Final Resolution Date: 29-Jun-99 Affected Technical Specifications 5.2.2 Administrative Controls, Unit Staff 5.3.1 Administrative Controls, Unit Staff Qualifications 5.5.4 Administrative Controls, Radioactive Effluent Controls Program 5.6.4 Administrative Controls, Monthly Operating Reports 5.7 Administrative Controls, High Radiation Area 05-Aug-02 Traveler Rev. 2. Copyright (C) 2002, EXCEL Services Corporation. Use by EXCEL Services associates, utility clients, and the U.S. Nuclear Regulatory Commission is granted. All other use without written permission is prohibited.

TSTF-258, Rev 4 Justification:

1. Changes to Section 5.2, Organization

a. The requirements of 10 CFR 50.54(m)(2)(iii) and 50.54(k) adequately provide for shift manning. These regulations, 50.54(m)(2)(iii), require "when a nuclear power unit is in an operational mode other than cold shutdown or refueling, as defined by the unit's technical specifications, each licensee shall have a person holding a senior operator license for the nuclear power unit in the control room at all times. In addition to this senior operator, for each fueled nuclear power unit, a licensed operator or senior operator shall be present at the controls at all times." Further, 50.54(k) requires "An operator or senior operator licensed pursuant to part 55 of this chapter shall be present at the controls at all times during the operation of the facility." The ISTS 5.2.2.b requirements will be met through compliance with these regulations and is not required to be reiterated in the ISTS.

In the April 9, 1997 letter from C. Grimes to J. Davis, the staff proposed revising 5.2.2.c by adding "Shift crew composition shall meet the requirements stipulated herein and in 10 CFR 50.54(m)." Adding this sentence is a duplicative of the code of federal regulations since all licensees are required to meet 10 CFR 50.54.

b. Section 5.2.2.e. is revised from specific working hour limits to administrative procedures to control working hours. The proposed changes w ill provide reasonable assurance that impaired performance caused by excessive working hours will not jeopardize safe plant operation. Specific working hour limits are not otherwise required to be in the technical specifications under 10 CFR 50.36(c)(5). Specific controls for working hours of reactor plant staff are described in procedures that require a deliberate decision making process to minimize the potential for impaired personnel performance, and that established procedure control processes will provide sufficient control for changes to that procedure. These changes are consistent with the recommendations in the April 9, 1997 letter from C. Grimes to J. Davis. Additionally, the statement "Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the [Plant Superintendent] or his designee to ensure that excessive hours have not been assigned." is being deleted. There is no guidance in Generic Letter 82-12 that discusses these additional controls.

The additional requirement to have the Plant Manager (or his designee) review individual overtime on a monthly bases is unnecessary since sufficient administrative controls and policies exist, as well as the role of the individuals supervisors in supervising personnel prevent excessive or abuse of overtime.

c. Section 5.2.2.g is revised to eliminate the title of "Shift Technical Advisor (STA)." STAs are not used at all plants (the function may be fulfilled by one of the other on-shift individuals).

Therefore, 5.2.2.g is revised so that it does not imply that the STA and the Shift Supervisor must be different individuals. Option I of the Commission Policy Statement on Engineering Expertise on Shift is satisfied by assigning an individual with specified educational qualifications to each operating crew as one of the SROs (preferably the shift supervisor) required by 10 CFR 50.54(m)(2)(i) to provide the technical expertise on shift. However, the 5.2.2.g wording of, "the STA shall provide... support to the Shift Supervisor...", is considered to be easily misinterpreted to require separate individuals. Therefore, the wording is revised so that the STA function may be provided by either a separate individual or the individual who also fulfills another role in the shift command structure.

Page l of 4

TSTF-258, Re-v 4

2.

Chances to 5.3, Unit Staff Qualifications.

a.

In Section 5.3.1, the second sentence is bracketed in its entirety. There may be cases were the entire unit staff are covered by the standard specified in the first sentence or there may be specific exceptions for specific positions that could then be specified by bracketing the entire sentence.

b. Definitions in 10 CFR 55.4 state: "Actively performing the functions of an operator or senior operator means that an individual has a position on the shift crew that requires the individual to be licensed as defined in the facility's technical specifications, and that...." Adding paragraph 5.3.2 ensures that there is no misunderstanding when complying with 10 CFR 55.4 requirements. Adding this paragraph is consistent with the recommendations in the April 9, 1997 letter from C. Grimes to J. Davis.

c... The April 9, 1997 letter from C. Grimes to J. Davis proposed a Reviewers Note in conjunction with the addition of paragraph 5.3.2. The Reviewer's Note stated: "The minimum staffing requirements stipulated in 10 CFR 50.54(m), for unit members actively performing the functions of an operator or senior operator, can be exceeded by stipulating the enhanced staffing requirements in paragraph 5.3.2." This Reviewer's Note is not required based on the discussions in Generic Letter 87-16 (Transmittal of NUREG-1262) which indicated that facilities can take credit for more than the minimum number of watchstanders required by Technical Specifications provided that there are administrative controls which assure that functions and duties are divided and rotated in a manner which provides each watchstander meaningful and significant opportunity to maintain proficiency in the performance of the functions of an operator and/or senior operator as appropriate. By stipulating enhanced staffing requirements in paragraph 5.3.2, when a licensee decided to change its staffing requirements, a license amendment request would have to be submitted, reviewed and approved before the staffing requirements could be made which may not be timely and is an unnecessary burden on the licensee's and NRC's resources.

3 Chanpcs to 5.5.4. Radioactive Effluent Controls Program.

After issuance of Generic Letter 89-01, 10 CFR 20 was updated. The NRC issued a draft Generic Letter, 93-XX, on proposed changes to STS NUREGS base on the new 10 CFR 20.

The proposed changes are consistent with the draft generic letter and the April 9, 1997 letter from C. Grimes to J. Davis with some exceptions noted below. The proposed changes maintain the same overall level of effluent control while retaining the operational flexibility that exists with current TS under the previous 10 CFR 20. This limitation (i.e., less than 10 times the concentration values...) provides reasonable assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within (1) the Section MI.A design objectives of appendix I to 10 CFR Part 50 and (2) restrictions authorized by 10 CFR 20.1301(e). These changes are intended to eliminate possible confusion or improper implementation of the revised 10 CFR 20 requirements. The recommendations in the April 9, 1997 letter uses the term "total body" in reference to the noble gas dose rate. This limit is based on the dosimetry of ICRP 2, and the correct term is "whole body" as shown in NUREG-1301, Specification 3.11.2.1, page 45. Additionally, some minor editorial changes were made from the recommendations in the April 9, 1997 letter.

The provisions of SR 3.0.2 are applied to the Radioactive Effluent Controls Program surveillance frequencies (5.5.4e.) to allow for scheduling flexibility. SR 3.0.2 permits a 25%

Page 2 of 4

TSTF-258, Rev 4 extension of the interval specified in the Frequency (31 days). Allowing a 25% extension in the frequency of performing the monthly cumulative dose and projected dose calculation for the current quarter/year will have no affect on outcome of the calculations.

3. Changes to 5.6.4, M1onthly Operating Reports. The reporting of pressurizer safety and relief valve failures and challenges is based on the guidance in NUREG-0694, "TMI-Related Requirements for New Operating Licensees." The guidance of NUREG-0694 states: "Assure that any failure of a PORV or safety valve to close will be reported to the NRC promptly. All challenges to the PORVs or safety valves should be documented in the annual report." NRC Generic Letter 97-02, "Revised Contents of the Monthly Operating Report" requests the submittal of less information in the monthly operating report. The generic letter identifies what needs to be reported to support the NRC Performance Indicator Program, and availability and capacity statistics. The generic letter does not specifically identify the need to report challenges to the pressurizer safety and relief valves. Mr. Marcel Harper, NRC (AEOD) was contacted and he indicated that this information was not required for the Performance Indicator Program and therefore would not need to be reported. Based on this information, it is acceptable to delete the requirement to provide documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves.

5. Chances to 5.7, High Radiation Area. Section 5.7 is revised in accordance with 10 CFR 20.1601(c) and updates the acceptable alternate controls to those given in 10 CFR 20.1601. These changes are consistent (with the exception provided below) with the draft Generic Letter (93-XX) on proposed changes to STS NUREGs based on the new 10 CFR 20 and the letter from C. Grimes, NRC, to J. Davis, NEI dated April 9, 1997. (The NRC proposed version of Section 5.7 provided in the April 9, 1997 letter is included in this traveler with the recommended changes marked.)

Changes to 5.7.1 d.4.(ii): In the event that communications are lost between an individual worker, and the Radiation Protection staff providing the remote surveillance, the worker should be able to continue to work in the area provided that the worker can communicate with other workers in the same area who are working on the same job and under the same RNWP, and provided that the communications remain satisfactory between these workers and the RP staff providing the remote surveillance..

Changes to 5.7.1.e and 5.7.2.e: Revised to allow any individual or group of individuals to enter a high-high radiation area (dose rates > 1 Rem/hr at 30 cm) when accompanied by an individual qualified in radiation protection procedures with a radiation dose rate monitoring device. The qualified individual is responsible for providing positive control and shall perform periodic radiation surveillances at the frequency specified in the RWP.

Furthermore, these continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry. Many plant's CTS requirements allow this option, which compliments the plant's practices of requiring qualified individual escort at all times during the work in a high-high radiation area. This option would provide adequate protection while (keeping with ALARA practices) minimizing exposure to the qualified individual.

Page 3 of 4

TSTF-258, Rev 4

Changes to 5.7.2a: Section 5.7.2a is revised to state "Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate..." This change is consistent with RG 8.38 Section 2.5 which indicates that the use of a locked door or one control point where positive control over personnel entry is exercised. Posting an individual to monitor a door provides positive controls over a high radiation area.

Changes to 5.7.2.a. 1: The Shift Foreman is only one of the many possible operations shift management positions who may be designated for the key control function. This change is similar to the wording of the NRC 7-28-95 letter to the Ownees Group Chairmen which identifies key control responsibility with the "shift supervisor, radiation protection manager, or his or her designee."

Changes to 5.7.2f. (deleting "that is controlled as a high radiation area"): The 5.7.2.f provision has applied (in previous STS as well as ISTS NUREGs) without the added constraint of having the larger area controlled as a high radiation area. It is not always practical to control such areas as a High Radiation Area (outside of these High-High Radiation Areas). The proposed change to the NRC proposed Model Specification would restore the requirement as it exists in ISTS NUREG Revl.

Page 4 of 4

High Radiation Area 5.7 INSERT F TSTF-258, Rev 4 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceedinq 1.0 rem/hour at 30 centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of Radiation work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assi gned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area; or

2.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or (continued)

High Radiation Area 5.7 INSERT F TSTF-258, Rev 4 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 centimeters from the Radiation source or from any surface Penetrated bv the Radiation (continued)

4.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowled eable of them.

These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

High Radiation Area 5.7 INSERT F TSTF-258, Rev 4 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation source or from anv Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any surface Penetrated by the Radiation

a.

Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:

1.

All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee.

2.

Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b.

Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or (continued)

High Radiation Area 5.7 INSERT F TSTF-258, Rev 4 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiartion source or from anX Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation source or from any Surface Penetrated by the Radiation (continued)

2.

A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area, or

3.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area.

4.

In those cases where options (2) and (3),

above, are impractical or determined to be inconsistent with the "AS LOW AS is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

e.

Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them..

These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas.

This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

(continued)

High Radiation Area 5.7 INSERT F TSTF-258, Rev 4 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation source or from any Surface Penetrated by the Radiation (continued)

f.

Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

TSTF-258, Rev 4 INSERT A The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

INSERT B 5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Reactor Operator (SRO) and a licensed reactor operator (RO) are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

INSERT C to ten times the concentration values in Appendix B, Table 2, column 2 to 10 CFR 20.1001-20.2402.

INSERT D shall be in accordance with the following:

i. For noble gases: a dose rate

500 mrem/yr to the whole body and a dose rate 5 3000 mrem/yr to the skin, and

2. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate

1500 mrem/yr to any organ; INSERT E The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent controls Program surveillance frequency.

INSERT G Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

Oranzaio Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

Two unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

b. A east one ct er (RO) shall presen n the control om when fuel is n the reactor In addition, whi the unit is iYODE 1 2, 3, 3 r 4, at least one licens Senior Reacto perator (SRO s hall be pre in the c trol room.,

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.t2 for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A (Health Physics Technician] shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

Administrative procedures shall e eveloped and implemented to limit the working ho rs of who perform safety related functions (e.g.

Licen s

d5S l

icensed h

eal th physicists, auxiliary operator,/an key ma in t

ena nc e"/-,' _ _

personnel 1£?; d loe v'0 ra1:

C

')

Adequate sh5Wt coverage shall be naintaine wlthout rou me heavy us f overtime.

The ob' ctive shall be to h ve opera rg personnel work an or 12] hour day, inal l

40 ur week while the un' is operating.

How er, in the e nt that unforeseen pAblems require subs tial amounts ff overtime to be us

, or during extende periods of shutdown for refue *ng, major maintenan

, or major plant modification, on temporary basis th following guideli s shall be follo d:

/

1. An in vidual should not be permitted to work ore than )

_16 hurs straight, excluding shift turnover time; (continued)

WOG STS 5.0-3 Rev 1, 04/07/95

Organization 5.2 5.2 Organization

/ S7-F-S Ai-,,

4 5.2.2 Unit Staff (continued) t individual should t be permitted work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24,ur period, nor re than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months iod, nor more t 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any, 7 day period, 1 excluding shi turnover time; /

A break at least 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed tween work p iods, including ift turnover time-Ex pt during extend shutdown periods the use ertime should be onsidered on an i ividual b sis and not for the e tire staff on a shtft.

Any deviation from the above guidelines shal in advance by the [Plant Superintendent) or accordance with approved administrative prol ihr levso geme ia anc 25ocedu 42 s

! an nwth documentation of the ba:

imouno of overtime w ked by unit irWig safety rel d functions

olled in accor afce with thp RC ng hours (Ge nc Letter

-12).

r@.

The [Operations Manager or Assistant Operations Manager]

shall hold an SRO license.

Shi A shal rovi e advisory technicaf suppor to the e~i V

in the areas of thermal hydraulics, rea or engineering, and plant analysis with regard to the safe operation of the unit. @

h shall meet the qualifications specified by the commission Policy Statement on Engineering Expertise on Shift.

WOG STS 5.0-4 Rev 1, 04/07/95

Unit Staff Qualifications 5.3

S7 -F-2&<

5.0 ADMINISTRATIVE CONTROLS X

5 5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of (Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable to the NRC staff].

v he staff not covered byoRegulatory Guide 1.80 shall meet or exceed the minimum qualifications of T egulations, Regulatory des, or ANSI Standards acceptable to NRC staff].

WOG STS 5.0-5 Rev 1, 04/07/95

Programs and Manuals 5.5 75 FF-2&8 5.5 Programs and Manuals X

f 5.5.4 Radioactive Effluent Controls Program (continued) be taken whenever the program limits are exceeded.

The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liqud effluents to unrestricted are conforming to oljI

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix 1;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; A

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundarylcon TrIAFng Wrthe o assoc e wi DHC FR 20! Pi7penddx B, Xble 2,,C1ung'

/

Bet

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; (continued)

WOG STS 5.0-9 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals i

5.5.4 Radioactive Effluent Controls Program (continued)

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public ue to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 ComDonent Cyclic or Transient Limit This program provides controls to track the FSAR, Section [ ],

cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with [Regulatory Guide 1.35, Revision 3, 1989J.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant PumD Flywheel InsDection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory.

Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

(continued)

WOG STS 5.0-10 Rev 1, 04/07/95

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

PI-W 5.6.4 Monthly Operating Reports Routine reports of operating statistics d

gfi>4n~l~rie c

P~'h pr>nr WOGW;r) ay<rte jef vaunts or Prwssur ize ft av!lsh be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

The individual specifications that address core operating 7

limits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic (continued)

WOG STS.

5.0-20 Rev 1, 04/07/95

[High Radiation Area]

i5.7]

5.0 ADMINISTRATIVE CONTROLS 6

( [5.7 High Radiation ea]

IF Rk

-If

/

I II i

I I

II I

II IIII III 5.7.1 Psuant to 10 CFR 20, paragraph 20. 01c), in lieu of the requirements of 10 CFR 20.1601, e high radiation area, as defined in 10 CFR 20, in which e intensity of radiation is

> 100 mrem/hr but < 1000 mrem r, shall be barricaded and conspicuously posted as a h radiation area and entrance thereto shall be controlled by re iring issuance of a Radiation Work Permit (RWP).

Individu s qualified in radiation protection procedures (e.g., [He th Physics Technicians]) or personnel continuously escort by such individuals may be exempt from the RWP issuance requ ement during the performance of their assigned duties in high r diation areas with exposure rates g 1000 mrem/hr, provided they e otherwise following plant radiation protection procedures f entry into such high radiation areas.

Any indi dual or group of individuals permitted to enter such areas all be provided with or accompanied by one or more the follo ng:

a A radiation monitoring device that continuously dicates the radiation dose rate in the area.

b. A radiation monitoring device that contin usly integrates the radiation dose rate in the area an larms when a preset integrated dose is received. Entry i o such areas with this monitoring device may be made ter the dose rate levels in the area have been estaished and personnel are aware of them.

/

c. An individual qualified in adiation protection procedures with a radiation dose ra monitoring device, who is responsible for providig positive control over the activities within th area and shall perform periodic radiation surveill ce at the frequency specified by the

[Radiation Prote ion Manager] in the RWP.

5.7.2 In addition to e requirements of Specification 5.7.1, areas wi radiation levels Ž 1000 mrem/hr shall be provided with locked continuously/guarded doors to prevent unauthorized entry an he keys shall/be maintained under the administrative control the Shift Footman on duty or health physics supervision. D s shall remain/locked except during periods of access by pers Inel under an approved RWP that shall specify the dose rate le s in (continued) i I, iKI I

IIIII I

I II II j

I WOG STS 5.0-24 Rev 1, 04/07/95

(High Radiation Area] v __t< t5.7 A5.7 Hi Radiation Area]

I -1 (ft -t61!> O 1.10 (continued) the imiedia work areas and the maximum allo le stay times for individua in those areas. In lieu of th tay time specifi tion of the RWP, direct or remo (such as closed circuit TV coeras) continuous surveillance maybe made by personnel qu ified in radiation protection pr cedures to provide positive posure control over the activitj s being performed within the area.

5.7.3 For individual high radiati areas with radiation levels of

> 1000 mrem/hr, accessibl to personnel, that are located with large areas such as rea or containment, where no enclosure ists for purposes of locki, or that cannot be continuously g ded, and where no enclosue can be reasonably constructed ar d the individual area, "at individual area shall be barricaed and conspicuously po ted, and a flashing light shall be Ativated as a warning device/

.l V WOG STS 5.0-25 Rev 1, 04/07/95

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

o unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

b.

least one,1Afensed Reactor erator (RO) shAr be pr in the con 1 room when fu is in the rea pr. In addition while the unit if in MODE 1, 2, or 4, at St one liV nsed Senior Re acor Operator 0

O) shall be esent in t e control room./

6Y@.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2 X for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A [Health Physics Technician] shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

e-r--'M rl

<. Administrative procedures shall be deve aped and implemented to limit the working hound of who perform safety related functions (e.g.

cee icensed_2ti lhealth physicists, auxiliary operators, n ey main n/

personne.

i.

o

'dov otoe (M ocJ Adequ e shift cove age shal l1e maintained withou n

hea use of over tme.

The obje

ve shall be to e

operating perso el work an [8 12] hour day, minal hour week ile the unit i operating.

How er, in the event that foreseen problms require substa iaI amounts of overtim to be used, o during extended iods of 7

shutdown or refueling, ajar maintenance or major p1 modifi tion, on a temporary basis the following guide ines shall e followed: /

/

(continued)

BWOG STS 5.0-3 Rev 1, 04/07/95

Organization 5.2 73 772-2 S58 5.2 Organization 5.2.2 Unit Staff (continued)

1. A ndividual sho gd not be permitted work more than 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months straig, excluding shift mover time; An individu s

hould not be pe ted to work more an 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months i any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months perio nor more than 24 urs in any 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months period, nor e than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months i any 7 day eriod, all excludin shift turnover ti

3. A eak of at least 8 urs should be all ed between rk periods, includi g shift turnover me;

4. Except during ext ded shutdown per ds, the use of overtime should e considered on a individual bas se,.A d not for the entire staff on a sht=

Any deviation from the above guidelines s a e autorized in advance by the [Plant Superintendent] or desi nee. in accordance with approved administrativeRoeueLlys, or 7%

le 0fo vanqemop&*: in accodance S ethetbih thdocumentation of the basis for granting 6-ntr s shall b included the proce rs such a

\\

du NRme ohall e viewe intly bate nt perinit or his g

to sure Lh)xcessir

\\ Hous hav~not een aSi, ed. JRutine dvainto h

aeguidelines hs9aiborized._

/ h mad fovertinez4orked by uiX~staff me is l

A r ng safety railated functio0 shall be mited and J

,cwrled in acr fiance with Nh RC Pol c'ttment r

_ okng hours eneric Letter/2K2-12).

/__

The [Operations Manager or Assistant Oerations Managem

/4 shall hold an SRO license.

n,+ c e-1 e-crrh The-Sfi~ft chni Advidf

(

shall orove advisory Xecnicl sppot t th Ls~flSkp~vine H~vin the areas of thermal hydraulics, reactor engineering, and plant analysis with re ard to the safe operation of the unit. 4 n

ad ionX,1rhe,§M shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

BWOG STS 5.0-4 Rev 1, 04/07/95

Unit Staff Qualifications 5.3 7I25 7rF-.2LE 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff.or by specifying individual position qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of [Regulatory Guide 1.8, Revision 2, 1987, or more decent revisions, or ANSI Standard acceptable to the NRC staff].

vhe staff not covered by v egulatory Guide 1.80shall meet or exceed the minimum qualifications of (fRegulations, Regulatory Guides, or ANSI Standards acceptable Po NRC staff].

BWOG STS 5.0-5 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Proqram (continued) be taken whenever the program limits are exceeded.

The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, A--,

conforming to (1

i 20 en umt-(._if.um(IE73

c.

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

(;;a_ -he s'kp

g.

Limitations on the dose rate resultingfom radioactive material releasedqI' aseous effluents to areas eyon the site boundaryrconfaftPintsth dogescbdw1t Lr

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; (continued)

(continued)

BWOG STS 5.0-9 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j.

Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

rAo^.d 4fA s;b'/

°,'Sa 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section

]

cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations.

The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with [Regulatory Guide 1.35, Revision 3, 1989).

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendation of Regulatory position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

(continued)

BWOG STS

5. 0-10 Rev 1, 04/07/95

Reporting Requirements 5.6 5.6 Reporting Requirements (continued)

X-S 5.6.4 Monthly Operating Reobrts rins~hfidinop c2Ri1lE;~

a 1 ch3~hnes tlvre pra~ri!

tst~ratdodief valef or pressaffizer safety valw!,~salb submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

rhe individual specifications that address core operating 7

Flimits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling System (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic (continued)

BWOG STS S.

0 20 Rev 1, 04/07/95

[High Radiation Area]

[5.7]

/-f-2 SFK 3

( tisef7L F) 5.0 ADMINISTRATIVE CONTROLS q

I O[5.7 High Radiation Area]

5.7.1 P suant to 10 CFR 20, par aph 20.1601(c), in lieu of e

equirements of 10 CFR 20 601, each high radiation ar

, as defined in 10 CFR 20, i which the intensity of radi ion is

> 100 mrem/hr but < 1 0 mrem/hr, shall be barricad and conspicuously poste as a high radiation area and ntrance thereto shall be controll by requiring issuance of a diation Work Permit (RWP).

I dividuals qualified in radia on protection procedures (e..,

[Health Physics Technicia

) or personnel continuously scorted by such individuals ay be exempt from the RWP issuanc requirement during the perfp mance of their assigned duties in igh radiation areas with ex sure rates < 1000 mrem/hr, provided hey are otherwise followin plant radiation protection proced es for entry into such hig radiation areas.

Any ndividual or group of mdi duals permitted to enter such aras shall be provided with accompanied by one or more of the f lowing:

a. A radiation monitor g device that continuously indicates the radiation dose ate in the area.

/ b. A radiation mon oring device that continuously integrate the radiation ose rate in the area and alarms when a p set integrated se is received.

Entry into such areas w h

/

this monit 5ing device may be made after the dose r e levels in he area have been established and pers nel are aware o them.

c. An i ividual qualified in radiation protec on procedures wit a radiation dose rate monitoring dev e, who is r ponsible for providing positive cont over the tivities within the area and shall rform periodic radiation surveillance at the frequecy specified by the

[Radiation Protection Manager] i e RWP.

5.7.2 n addition to the requirements o Specification 5.7.1, areas/ ith

/

radiation levels 2 1000 mremfhr hall be provided with locke or continuously guarded doors to revent unauthorized entry Xd the keys shall be maintained under the administrative controY of the Shift Foreman on duty or hiailth physics supervision.

Doors shall remain locked except dur~ing periods of access by personnel

\\;'F'/_

\\

~

onnF; nlod I

kuul IL. II IUCUJ BWOG STS 5.0-24 Rev 1, 04/07/95

[High Radiation Area]

(5.7]

a 7F 7.- -

T4

/ S[.7 High. R aion -Area

!57.7 continued)

/

under an approved R that shall specify the dose r levels in the immediate war areas and the maximum allowabi stay times for individuals in ose areas. In lieu of the st time specificatio of the RWP, direct or remote (sch as closed circuit TV cameras continuous surveillance may be ade by personnel qualifie in radiation protection proced es to provide positive exposu control over the activities b ng performed within the are>/

5.7.3 r individual high radiation ar as with radiation levels of

> 1000 mrem/hr, accessible to ersonnel, that are located withi large areas such as reactor ontainment, where no enclosure e sts for purposes of locking, that cannot be continuously gua ed, and where no enclosure n be reasonably constructed arou the individual area, that ndividual area shall be barricad and conspicuously.poste and a flashing light shall be a ivated as a warning device.

I

\\

f I

x _

A_

I/

BWOG STS 5.0-25 Rev 1, 04/07/95

Organization 5.2 T-: 7F-.25Tc8 5.2 Organization AfA4 Yq 5.2.2 Unit Staff (continued) shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4.

Two unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

(b.

At ast one licen d Reactor Operat (RO) shall be sent the control ram when fuel is the reactor.

addition, whi the unit is in DE 1, 2, 3, orn, at least one license Senior Reactor erator (SRO) sh be present /

in the co rol room.

'0.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2 @

i for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A (Health Physics Technician] shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

I Jo I E.

Administrative procedures shallLbe-developed and implementi to limit the working hours of (u4{'? sWff) who perform safety related functions (e.g.,lIicensedJ W, licensedo health physicists, auxiliary operators and key maintenance personnel)b SeC Opere6ozr CS4O)

'cf c

I-:

" e"SZ' dequa shitco age snal maintained wifa ruti hea use of ov time. The ojective shall be have o rating per nnel work an or 12] hour day nominal 0 hour0 days 0 hours 0 weeks 0 months wee while the uni is operating. Hwever, in the event th unforeseen pr ems require sub antial amounts of over ime to be used or during extend periods of shut wn for refueli, major maintena e, or major plan ma fication, on a emporary basis t following guide new shall be followed

1. An indiv, dual should not be ermitted to wo more th, 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnoverf time;

/

ed (continued)

CEOG STS 5.0-3 Rev 1, 04/07/95

Organization 5.2

/ TS 7-F-2 !2 5.2 Organization kw q1

_.i 5.2.2 Unit Staff (continued) amoupt of overtim3,worked by unit Forging safety stlated functions foiled in aerdance with thpfARC Aing hours ieneric Letter Bf-12).

The [Operations Manager or Assistant Operations Manager]

shall hold an SRO license.

"I Shi shall ovde advisory technica support to the S

vi in the areas of thermal hydraulics, reactor engineering, and plant analysswith regard to the safe operation of the unit.

i ;,-;1,jh)ea isTAtshall meet the qualifications specified by theC~oiThWi Policy Statement on Engineering Expertise on Shift.

CEOG STS 5.0-4 Rev 1, 04/07/95 4

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS

/ 5 / 7-Z 5T-6 lev 5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications.

Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 SC Each member of the unit staff shall meet or exceed the minimum qualifications of [Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable lo the NRC staff].

ahe staff not covered by &egulatory Guide 1.W shall meet or exceed the minimum qualifications of ftegulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff).

ID CEOG STS S.0-E Rev 1, 04/07/95

Programs and Manuals 5.5 T5 r7F-2s 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls ProQram (continued) achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance..

with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas.

conforming to 1 CeRu

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; gr7

{h b

g. Limitations on the dose rate resultingjfrom radi ctive material released in gaseous effluents to areas beyond the site bogrt~rcy'ng Jto-,the dosAo,4sso

)(co Apjx dix 113

~ble 2, um,P'J l

(continued)

CEOG STS 5.0-9 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals TsT 7-Z 7 8s-5.5.4 Radioactive Effluent Controls ProQram (continued)

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j.

Limitations on the annual dose or dose commitment to any member of the publi due to releases of radioactivity and to radiation from uranium fue cycle sources, conforming to 40 CFR 190.

' LexrL4 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR Section [

]

cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with [Regulatory Guide 1.35, Revision 3, 1989].

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of regulatory position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.

(continued)

CEOG STS 5.0-10 Rev 1, 04/07/95 I

Reporting Requirements 5.6 5.6 Reporting Requirements m2 5.6.2 Annual Radiological Environmental Operating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979].

[The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.] In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report NOTE A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience Ha al iengh (continued)

(continued)

CEOG STS 5.0-20 Rev 1. 04/07/95

[High Radiation Area]

(5.7]

r

[5.7 High Rajd*tion Area] T mi2S-LI q

-S..

5.7.

continued)

(

under an approved RWP at shall specify the dose rat evels in the immediate work eas and the maximum allowable ay times for individuals in t se areas.

In lieu of the stay ime specification the RWP, direct or remote (s as closed circuit TV cameras) ontinuous surveillance may be de by personnel qualifie n radiation protection procedu s to provide positive exposu control over the activities b g performed within the area 5.7.3 For individual high radiation eas with radiation levels of

> 1000 mrem/hr, accessible personnel, that are located within large areas such as react containment, where no enclosure exi s

for purposes of locking/or that cannot be continuously guar d, and where no enclosurycan be reasonably constructed arou the individual area, that individual area shall be barricad and conspicuously posh4d, and a flashing light shall be a ivated as a warning device.

CEOG STS 5.0-26 Rev 1, 04/07/95

Reporting Requirements 5.6

-7FS 7 /F-Z S-8 5.6 Reporting Requirements.Z747 S

5.6.4 Monthly Operatina ReDorts (continued)

(K<ves-F res zer sa~ty v shall e su ntted on a monthly basis no later t an each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COIR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

rhe individual specifications that address core operating 7

Flimits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, critically, and hydrostatic (continued)

CEOG STS 5.0-21 Rev 1, 04/07/95

[High Radiation Area]

(5.7]

5.0 ADMINISTRATIVE CONTROLS (I7Sc

)

/i7-F-2 s-(5.7 Hi adiation Area]

F

/

5..

Pursuant to 10 CFR 20, paragr 20.1601(c), in lieu of the requirements of 10 CFR 20.

1, each high radiation area, as defined in 10 CFR 20, in ich the intensity of radiation is

> 100 mrem/hr but < 1 mrem/hr, shall be barricaded and conspicuously poste as a high radiation area and entrance ereto shall be control by requiring issuance of a Radiation ork Permit (RWP).

ndividuals qualified in radiation prot tion procedures

.g., [Health Physics Technicians]) or sonnel continuousy escorted by such individuals may be empt from t RWP issuance requirement during the pe ormance of their assi ed duties in high radiation areas with posure rates 00 mrem/hr, provided they are otherwis ollowing plant diation protection procedures for entr into such high radiation areas.

Any individual or group of indivi als permitted to enter such areas shall be provided with or ccompanied by one or more of the following:

a. A radiation monitor g device that continuously indicates the radiation dose ra in the area.

b. A radiation itoring device that continuously integrates the radiati dose rate in the area and alarms when a preset integrat dose is received. Entry into such areas with this monitor ng device may be made after the dose rate levels in the ea have been established and personnel are aware of t

c. An individual qualified in radiation protection ocedures with a radiation dose rate monitoring device ho is responsible for providing positive controver the activities within the area and shall p orm periodic radiation surveillance at the frequency specified by the

[Radiation Protection Manager] i Mhe RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels 2 1000 mrywfhr shall be provided with locked or,,

continuously guarded doops to prevent unauthorized entry and the keys shall be maintai 'd under the administrative control o,<the Shift Foreman on d y or health physics supervision. Doors shall remain locked e pt during periods of access by perso el I

II

/

(continued)

CEOG STS 5.0-25 Rev 1, 04/07/95

Organization 5.2 FS 7/7-2-5 5.2 Organization X

5.2.2 Unit Staff (continued) shall be assigned for each control room from which a reactor is operating in MODES 1, 2, or 3.

Two unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

b. At least one V ensed Reactor erator (RO) s be prese in the cont room when fugris in the react.

In

addition, ile the unit in MODE 1, 2, 3, at least ne license Senior Reactor perator (SRO) 11 be presen in the c trol room.

rrr_-

kfl/

0 0--i, 0.

0 Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.g m

for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

A [Health Physics Technician] shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

Administrative procedures shall be eveloped and implemented to limit the working hours of s

who perform safety related functions (e.g.V icensed (S ), licensed health physicists, auxilaryeoperat en personnel, ft

(

&4sa ope C.

&/

Adshquao oshift coverage, mall be maintane, or aorplan heoii tse of onatempr ybjective/shall be to have/

0 <ating personn twork an [8 or Ij~ hour day, oia

\\

~Ofhour week whj'f the unit is op a aing. Howevevi the\\

event that u foeseen problems equire substanta amunts of overtim vo be used, or dupn extended perilso shutdown or refueling, majo maintenance, ormjor plant 1

modif p~ion, on a tempor;y basis the fol oig guidelln~

sha be followed:

An individual srould not be permit d to work moe than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months strai4ht, excluding shif turnover tie; (continued)

BWR/4 STS 5.0-3 Rev 1, 04/07/95

Organization 5.2 T7 57-z 3 5.2 Organization Unit Staff (continued) 5.2.2 Hfie worked 4yvTnit staffjm-bers elated fuopCions shall e limited at dance 'th the NRC icy Statemepe ric pJeter 82-12)

/

V P I

The [Operations Manager or Assistant Operations Manager]

shall hold an SRO license.

Th it T ical iso TA shal rvdeadvisory g ;

Ii Xhf-t T

technical support to the(S44 u

iso in the areas A n IV, Lao of thermal hydraulics, reactor engineering, and plant I

with reqard to the safe operation of the unit. f gon e SA shall meet the qualifications specified by

'i iiG ssioF-Pbl icy Statement. on Engineering Expertise on Shift.

BWR/4 STS 5.0-4 Rev 1, 04/07/95

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of [Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable to the NRC staff].

@ he staff not covered by PRegulatory Guide 1.81 shall meet or exceed the minimum qualifications of6DRegulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff].

BWR/4 STS 5.0-5 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals

/ZAA M 5.5.4 Radioactive Effluent Controls Program (continued) achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming totlQe 25 2

ppeadt-B,, 5Te2 u

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR SO, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every.31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas eyon the site boundaryvtonditmmng > Lrhe oo assseiatid'W1 t])

(continued)

BWR/4 STS 5.0-9 Rev 1, 04/07/95

Programs and Manuals 5.5 5.5 Programs and Manuals 7

B5-27-2&

,R=W a 5.5.4 Radioactive Effluent Controls Program (continued)

h.

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i.

Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

j.

Limitations on the annual dose or dose commitment to any member of the publi cdue to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190; and ey,,J-.h sYe-6,ou, d

k. Limitations on venting and purging of the Mark II containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable (in BWR/4s with Mark II containments).

COmnonent Cyclic or Transient Limit 5.5.5 This program provides controls to track the FSAR Section [ ],

cyclic and transient occurrences to ensure that components are maintained within the design limits.

Pre-Stressed Concrete Containment Tendon Surveillance Program 5.5.6 This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity.

The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with [Regulatory Guide 1.35, Revision 3, 1989].

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

(continued)

BWR/4 STS 5.0-10 Rev 1, 04/07/95

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Ooeratinc Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C; The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979].

[The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.]

In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

NOTE-------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Monthly Operating Reoorts Routine reports of operating statistics and shutdown exerien ce i !2d~inJfocumenii onor e

o safe ntyelie (continued)

BWR/4 STS

5. 0-19 Rev 1, 04/07/95

Reporting Requirements 5.6 7Zh rr-zZ 5.6 Reporting Requirements X

7 5.6.4 Monthly Operating-ReDorts (continued) via",s.hall be submitted on a monthly basis no later than the 15th oeach month following the calendar month covered by the report.'

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the fol owing:

rThe individual specifications that address core operating 7

limits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those-previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff.Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a. RCS pressure and temperature limits for heatup, cooldown, low temperature operation, critically, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

BWR/4 STS 5.0-20 Rev 1, 04/07/95

[High Radiation Area]

[5.7]

T*Ff-2s E 5.0 ADMINISTRATIVE CONTROLS t5.7High Radiation Area.]

5.7.1 Pursu >

o 10 CFR 20, paragraph 20.1601(c), X ieu of the requ ements of 10 CFR 20.1601, each high p~iation area, as d

ned in 10 CFR 20, in which the inten ty of radiation is 100 mrem/hr but < 1000 mrem/hr, shal be barricaded and conspicuously posted as a high radia on area and entrance thereto shall be controlled by requiring i uance of a Radiation Work Permit (RWP).

Individuals quali Led in radiation protection procedures (e.g., (Health Phys' s Technicians]) or personnel continuously escorted by suc individuals may be exempt from the RWP issuance requirement d ing the performance of their assigned duties in high radiation eas with exposure rates S 1000 mrem/hr, provided they are otherse following plant radiation protection procedures for entry to such high radiation areas.

Any individual or roup of individuals permitted to enter such areas shall be ovided with or accompanied by one or more of following:

a. A rad) 4 ion monitoring-device that continuously ind ates the iadiation dose rate in the area.

b.

radiation monitoring device that continuousl integrates the radiation dose rate in the area and ala s when a preset

, integrated dose is received. Entry into s h areas with this monitoring device may be made after he dose rate levels in the area have been establish personnel are

/

oaware of them.

c. An individual qualified in radia on protection procedures

/ A with a radiation dose rate moni oring device, who is responsible for providing posftive control over the activities within the area nd shall perform periodic radiation surveillance e frequency specified by the

[Radiation Protection 3 nager] in the RWP.

5.7.2 In addition to the requipements of Specification 5.7.1, areas with radiation levels 2 100p'mrem/hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the kes shall be maintainee'under the administrative control of the Shif Foreman on duty health physics supervision. Doors shall resin locked except firing periods of access by personnel under an/pproved RWP that sha specify the dose rate levels in the immediate work

/

(contnued i@

I 11 II I

i I

iIIi I

BWR/4 STS 5.0-23 Rev 1, 04/07/95

High Radiation Area 7-2 -

/ I(F-5.71 r [.7High !d tion Area]

l 5 <

continued)//

[

/

areas and the maximum -

able stay times for indiX asil those areas.

In ii of the stay time specificafn of the RWP, direct or remote uch as closed circuit TV c as) continuous surveillance m be made by personnel qualif d in radiation protection prcedures to provide positive posure control over the activi es being performed within t area.

5.7.3 For i ividual high radiation areas th radiation levels of

> 1 0 mrem/.hr, accessible to per nel, that are located within I e areas such as reactor con inment, where no enclosure exist or purposes of locking, or t cannot be continuously guarded and where no enclosure can b reasonably constructed around individual area, that indi dual area shall be barricaded d

conspicuously posted, a flashing light shall be activ ed as a warning device.

BWR/4 STS 5.0-24 Rev 1, 04/07/95

Organization 5.2 5.2 Organization T *-F-Z, M

5.2.2 Unit Staff (continued) shall be assigned for is operating in MODES each control room from which a.

reactor 1, 2, or 3.

Two unit sites with both units shutdown or defueled require a total of three non-licensed operators for the two units.

b. At least one 1 ensed Reactor Op ator (RO) sheh be present in the contr room when fueler in the rea.r. In

addition, ile the unit is n MODE 1, 2, 3, at least ne licensed enior Reactor 0 rator (SRO) sall be presen in the co rol room.

/

I)

(k cc F_

0J.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.

for a period of time not be exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

B A [Health Physics Technician] shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

=

Administrative procedures shall be developed and implemented to limit the working hours of 6isj-s f who perform safety related functions (e.g.

eed

, licensed IV health physicists. auxiliary operatorsan keymai personnelQ, O

(S" 0"

Orez

,o4,8 pr 0I Adequ e shift cover e shall be main ied without Whet yse of over

e. The objecti shall be to h e erating perso el work an [8 or 2] hour day, n inal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week, hile the unit is perating.

How er, in the event that foreseen proble require substa ial amounts of overti to be used, or ring extended nods of shutdo for refueling, m jor maintenance, or major plan modifcation, on a temp ary basis the f, lowing guidel nes

-sha be followed:

/

(continued)

BWR/6 STS 5.0-3 Rev 1, 04/07/95

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

1.

individual sho d not be permit d to work more th 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months strai

, excluding shi turnover time; An individ should not be p itted to work mor than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months n any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per d, nor more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, no more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months n any 7 d period, all exclu ng shift turnover e;

3.

break of at least hours should be al wed between work periods, inc ding shift turnove ime;

4. Except durin extended shutdown pe ods, the use of o---

overtime shudbe considered onio individual bas f'nd XI~r~er /1 not for e entire staff on a s fft.-

)

Any deviation from the above guidelines sha euthorized in advance by the tPlant Superintendent or

esignee, rn a

cord le with approved administrative ent on r

h§-evel>f maneift in ac-c'ordan~s~-Ma}<hd Th edu eratins documenr of the basis for granting a

s shal sacludede the proq caures such tfi b

iteomi ssl rtio i shallteme on monthly bgie inhg E

Pleris hperinte nt] or his.i ne ensure tha.'excessW Bas h

~e not been ioe otn dvainr

&Nfd 9Y~tlS s53V)0)uthorized.

/ Te amount overtime workAr by unit Stjt members

/

eform g safety re at - functi ons st1 be limited4n C:

cot v ed in accordan-ce with the NJK Policy Stat znt on

/

wo ~ng hours (GeV tic Letter 82-2) v 0.

The [Operations Manager or Assistant Operations Manager]

shall hold an SRO license..,

t~~i.

5i<SifTecMu1cal A;Wf'or 41k-sh advisory technical support to-the(sh t-u orlsLgn in the areas JACn

aV-4aJ of thermal hydraulics, reactor engineering, and plant

\\s____----~'

analysis with-reqard to the safe operation of the unit.

,--~~~~~~^>

__(addJI-Tbn, JnW STApshall meet the qualifications specified by t t

g

, >M'~the-Commis-si-on Policy Statement on Engineering Expertise on

\\

i c tJ 'mp IJ Shift.

BWR/6 STS 5.0-4 Rev 1, 04/07/95

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS

/T S 7--

2 S-5.3 Unit Staff Qualifications Reviewer's Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications.

Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special

-qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of [Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable to the NRC staff].

M The staff not covered by Regulatory Guide 1.80 shall meet or exceed the minimum qualifications of cRegulations, Regulatory (Z:lIZ-yt.,9 Guides, or ANSI Standards acceptable to NRC staff].

BWR/6 STS 5.0-5 Rev 1, 04/07/95

Programs and Manuals 5.5 7T3 Tf-2s 5.5 Programs and Manuals fleF-.

5.5.4 Radioactive Effluent Controls Program (continued) the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a.

Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b.

Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to FR

, Appeqd, lB.

We

J 2

2I-scf wo2

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d.

Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e.

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f.

Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

(

A s.k

g.

Limitations on the dose rate resulting from radi activ material released in gaseous effluents to areas be ond the site boundar conf ing he 05 sso

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each (continued)

(conti nued)

BWR/6 STS 5.0-9 Rev 1, 04/07/95

Programs and Manuals 5.5 7ys 7-F-2g8 5.5 Programs and Manuals RI-f t4 5.5.4 Radioactive Effluent Controls Program (continued) unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j.

Limitations on the annual dose or dose commitment to any member of the publi due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.5 Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section [ ],

cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity. The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with [Regulatory Guide 1.35, Revision 3, 1989].

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.

5.5.7 Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components including applicable supports. The program shall include the following:

(continued)

BWR/6 STS

5. 0-10 Rev 1, 04/07/95

Reporting Requirements 5.6 T7s 7TF-7-s-5 5.6 Reporting Requirements 5.6.2 Annual Radiological Environmental Onerating Report (continued)

(ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979].

[The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.] In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release ReDort

- - - - - -- - - - - - - -NOTE-- - - - - - -- - - - - - - -

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Monthly Operating Reports Rotn eot f opgratinq statisticsAd shutdown experience Roe~dnge rmenot!

o 11 c a n o

,3Crnae (continued)

(continued)

BWR/6 STS 5.0-19 Rev 1, 04/07/95

Reporting Requirements 5.6 5.6 Reporting Requirements 7-5.6.4 Monthly Operating Reports (continued) shall be submitted on a monthly basis no later than the 15th cffheach month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT MCOLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

rThe individual specifications that address core operating Flimits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates shall be established and documented in the PTLR for the following:

(continued)

BWR/6 STS5 5.0-20 Rev 1, 04/07/95

[High Radiation Area]

[5.7]

T7 TF-2-S0 7-I 4C 5.0 ADMINISTRATIVE CONTROLS k

a tt

[5.7 HighEadiation Area]

5.7 Pursuant to 10 CFR 20 p ragraph 20.1601(c), in lieu of e

requirements of 10 R 20.1601, each high radiation ar, as defined in 10 CFR 0, in which the intensity of radi ion is

> 100 mrem/hr b

< 1000 mrem/hr, shall be barrica d and conspicuously osted as a high radiation area an entrance thereto shall be co rolled by requiring issuance of a adiation Work Permit (Ru). Individuals qualified in radi ion protection procedur s (e.g., [Health Physics Technici s]) or personnel conti ously escorted by such individually be exempt from the RWP ssuance requirement during the per ormance of their assigned du es in high radiation areas with osure rates < 1000 mrem/hr, ovided they are otherwise followi plant radiation protection procedures for entry into such h radiation areas.

Any individual or group of in viduals permitted to enter such areas shall be provided wit or accompanied by one or more of th following:

a. A radiation moni ring device that continuously indica s the radiation se rate in the area.

b. A radiatio monitoring device that continuously tegrates the radi ion dose rate in the area and alarms en a preset integr ed dose is received.

Entry into suc areas with this nitoring device may be made after th dose rate leves in the area have been established d personnel are a Wre of them.

c. An individual qualified in radiatio protection procedures with a radiation dose rate monitorng device, who is responsible for providing positive control over the activities within the area an shall perform periodic radiation surveillance at th frequency specified by the

[Radiation Protection Mana r] in the RWP.

.5.7.2 In addition to the requiryments of Specification 5.7.1, areas with,"

-aradiation levels 2 1000, rem/hr shall be provided with locked orf-continuously guarded Coors to prevent unauthorized entry and tAfie keys shall be maint ned under the administrative control or'the Shift Foreman on d y or health physics supervision.

Doors shall remain locked ex pt during periods of access by personnel I

I

.1/

(-conti~nuedL-/

BWR/6 STS 5.0-24 Rev 1, 04/07/95

[High Radiation Area]

[5.7]

High Radiation Area)

W 4

5.7.

(cntinued) under an approved RWP t shall specify the dose rate levels in the immediate work ar s and the maximum allowable stay times or individuals in thos areas.

In lieu of the stay time specification of e RWP, direct or remote (such as clos circuit TV cameras) coninuous surveillance may be made by per onnel qualified in Xadiation protection procedures to pro de positive exposure c trol over the activities being perfo d within the area.

/

5.7.3 Fo individual high radiation areas with Radiation levels of 1000 mrem/hr, accessible to personnel/that are located within arge areas such as reactor containmey, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed a-ound the individual area, that individua)/area shall be barricaded and conspicuously posted, and a f)'ashing light shall be activat as a l

_warning device.

BWR/6 STS 5.0-25 Rev 1, 04/07/95

?r-vpz'sed ecC74C', £7 5.r7 f 4A 4fri/ 19l 7 F

e 2N1High Radiation Area 5.0

-s 772S ADMINISTRATIVE CONTROLS

-4 5.7 High Radiat1on Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall b applied to high radiation areas in place of the controls required by paragraph 20.1601(a) and (b) of 10 CFR Part 20:

S.7.1 Rilph Radiation Areas with Dose Rates Not Exceedinq 1.0 rem/hour at 30 Centimeters from the Radiation Source or from Any Surface Penetrated by the Rldialion-

a.

Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area.

Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b.

Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the imoediate work area(s) and other.appropriate radiation protection equipment and measures.

c.

Individuals jualified-in radiation protection procedures s2 iciz and personnel

-7~itllnuos1y escorted by s-iuithdividuals may be exempted from the requirement for an RWP or equivalent while X

performing their assigned duties provided that they are following plant radiation protection procedures for entry to, exit from, and work in such areas.

d.

Each individual or group entering such an area shall possess:

1.

A radiation monitoring device that continuously displays radiation dose rates in the area; or Continued P1ODEL SPECIFICATION s.0-16 ADMINISTRATIVE CoNTROLS

High Radiation Area 5.7 High Radiation Area 7_-7' -2w.YS 5.7.1 (continued)

2.

A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint, or

3.

A radiation monitoring device that continuousi transmits dose rate and cumulative dose o a reaote recetiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area, or

4.

A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, I

(i)

Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (11i) ivid; ~xs ;.1 Ser. IlAc..,ee Be under the surveillance as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to c" unicate w 5.7.2

e.

Except forindivldul gl fied in radiation protection 1

proceduresi4 entry intoti43 areasdiNJOhn made only ater P

dose rates in thnart, ii d tertIned and entry personnel are of the-Hich Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from Any Surface Penetrated by the Radiation, but Less than 500 rads/hour at I

&eter from the Radiation Source or from Any Surface Penetrated bv the Rad1aton:

a.

Each entryway to such an area shall be conspicuously posted

-as a high radiation area and shall be provided with a locked

.Continued MOOEL SPECIFICATION 5.0-17 ADMINISTRATIVE COTROLS

( These continuously escorted personnel will receive a pre-job briefing prior to entr~

such areas, This dose rate determination. knowledge, and pre-job briefing does not require documentation prior to initial entry.

I i

nto)

-

o1 High Radiation Area 5.7 5.7 High Radiation Area Ts 7F-Zs.,

5.7.2 door or gate

.tMe~

n tn (continued addition:

sea,

1.

Al sds door and gate keys shall_.aintained wnder the an1stlve control i

hhft supervisor,

\\

radiation proteton ana org s or her designee.

oe)

2.

Doors and prtec soall rein rced pt d(rI

b.

Access

,an acv eit in-, each lucl afta sha be controlled by aeans of an RWP or equivalent that includes specification of radiation dose rates in the Imediate work area(s) and other appropriate radiation protection equipment and measures.

c.

Individuals qualified In radiation protection procedures say be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided te following plant radiation protection

\\-______

roc dures for entry to, exit from, and work in such arias.

d.

Each individual or group entering such an area shall possess:

1. A radiation monitoring device that continuously integrates the radiation rates in the area and alarms when the devic2's dose alarm setpoint is reached, with an appropriate alarm set;oint, or

2.

A radiation monitoring device that c=ntinuously transmits dose rate and csulative dose information to a rmote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the mans to comunicate with and ::ntrp ev hidjJuj2 Iii th

/,

or 0

O O'

-~

Continue4 M0OOEL SPECIFICATION

.- 8 fMNShAIEC-5.0-18 ACMINISTRATIYE CWMLS

S High Radiation Area 7.7 5.7 High Kadiation Area I S 7-F-,58

......... ~.

AJ 4 5.7.2 (cwntinued)

3.

A solf-iuding dosimtar (e.g., pocket Ionization caber or electronic dosimeter) and, (1)

Be umder the surveillance, as specified in the P or equivalent, while in the area, of an individual qualified in radiation protection prociures, qupped ith a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for confrolling personnel exposure within the area, or (ii)

Be under the surveillance as specified in the RWP or equivalent, while In the area, by seans of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with_

,E in 1g0°/

~

~ r

, or t

f i

z t

§

4.

In those cases where opffns(ZJ-3), oveire' ipractical or determined to be inconsistent with the "As Low As is Reasonably Achievable' principle, a radiation monitoring device that continuously displays f orF se4 radiation dose rates in the area.

Except for individuaT qualified in radiation rotect in procedures entry into such areas al ace only aftr dose rates in the rea hav en d&etirined and entry personnel are knowledgeabl e.r ti2.-.

/

f. Such individual areas that ari iina.largerare

\\

where no enclosure 0

[Je

-atW far puerpse as of locking

=

.ro enclosure can arsmabde be ccnstricsed around the ind f ig lih not be controlled by a locked door or gatehbt sha barriczdj lcearly visibles¢hn ih shall be a

as a warning devic2.

I.

(cn~l'w-5 jafsL O

hlo xn4 X/I C

)

~ /

,--cEM2gSPIQF 3*5-7 -D!_T;YE S4CKIROLS._

These continuously escorted personnel will receive a pre-job briefing prior to entry into]

\\ such areas. This dose rate determination. knowledge. and pre-job briefing does not require documentation prior to initial entry.

-

ML040620102

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