NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl
| ML20059J508 | |
| Person / Time | |
|---|---|
| Issue date: | 10/25/1993 |
| From: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-1430, RTR-NUREG-1431, RTR-NUREG-1432, RTR-NUREG-1433, RTR-NUREG-1434, RTR-NUREG-1449 NUDOCS 9311120240 | |
| Download: ML20059J508 (73) | |
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h UNITED STATES
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a-October 25, 1993 MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support, NRR FROM:
Christopher 1. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR
SUBJECT:
SUMMARY
OF OWNERS GROUPS MEETING ON THE IMPROVED STANDARD TECHNICAL SPECIFICATIONS: AUGUST 26 AND 27, 1993 On August 26 and 27, 1993, the Technical Specifications Branch (OTSB) met with the Owners Groups (0G) to discuss the status of activities to implement the i
Technical Specifications Improvement Program (TSIP) and the development of the Low Power and Shutdown (LPS) TS. The meeting attendees.are listed in.
The agenda for the meeting is presented in Enclosure 2.
I made a brief presentation on the status of the development of the LPS TS in support of the rule-making effort.
The rule change will involve requirements to reduce core damage frequency during LPS conditions.
OTSB is developing a redline strikeout package of STS to accompany the Rulemaking in. December 1993.
The OG was encouraged to initiate a dialogue with the staff on the LPS TS issues as these TS are being developed by the staff.
The OG said that NUMARC's role will focus on the industry's issues involved in the underlying technical requirements of NUREG 1449/SECY 93-190.
The NRC is considering developing a generic communication, which may be in the form of a 50.54f request for license anendment, an order, or a generic letter, to accompany the Commission's proposed rule.
During the meeting, we proposed a schedule to the OG to permit OG's input to the LPS TS.
The proposed schedule is as follows:
9/15/93 Redline-strikeout TS with Bases from the NRC contractor forwarded to OG 9/21/93 Proposals / comments from 0G for NRC review 10/13/93 OG to meet with staff on their proposals / comments OG to provide data left open in the Bases 10/30/93 Complete draft model TS to OG s
11/15-12/1/93 Comment resolution on draft TS between technical staff and OG 3Fo3 The OG stated that their LPS TS proposal will not mean the endorsement of the proposed shutdown policy and technical requirements.
OG also expected a yN discussion with Bill Russell on the role of non-safety systems in the j g f pg S o m'
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. October 25, 1993 1
regulatory requirements. The objective is to reduce regulatory burden by using features that previously have not been allowed for credit in TS.
At the last meeting, we gave the 0G our first draft of the LPS TS, and i
requested OG to provide screening results on major. issues.
The OG did not have any response during this meeting as they are deciding what course of action they will take regarding providing comments. At this meeting,-the OG indicated that they would still like to continue to have the opportunity to 1
participate in the LPS TS development.
7 We reported the progress on the revision of files on the STS for all NSSS vendors.
These revisions will eventually be entered onto the OTSB Bulletin Board.
The OG want to have an opportunity to certify the final version. We, through our contractor, will enter changes to the files chronologically by groups.
By the next meeting, we will provide the OG with a redline-strike out package from our contractor and a schedule for the remaining packages to be completed.
We informed the OG that NRR management has directed the staff to restructure i
the details in Section 5.0, Administrative Controls, and to determine which 5.0 sections can be relocated (Enclosure 3). We will attempt to develop criteria to justify the content of Section 5.0.
For the near term, we need Crystal River and Watts Bar to reconsider the content of Section 5.0.
For the long term, we will consider incorporating the findings of requirements in e
Section 5.0 to the upcoming rulemaking in December 1993.
The issue of fuel enrichment in Section 4.0 is being considered by the staff.
Baltimore Gas & Electric will most likely request an amendment; the staff will address this issue during the review of the Calvert Cliffs amendment request.
We informed the OG that the following conditions need to be satisfied to relocate the steam generator tube surveillance requirements to the administrative controls:
(1) the leakrate from primary system to secondary system is in the LCO, (2) the operability requirements are reflected in the Steam Generator Tube Surveillance Program (the Program), and (3) changes to the content of the Program must receive prior staff approval in a license amendment.
The OG will provide a new Traveler addressing these NRC concerns.
We discussed the TS 3.0.4 when applied to a mode change, both up and down.
The current TS may be ambiguous in permitting a change of mode down while entering an Action Statement-. We agreed to address this issue with specific-examples at the next meeting.
On NRC/ Industry Process and Administrative Issues, the OG commented that there were errors in the earlier STS change packages because of using the term "All i
Owners Groups (A0G)." OTSB will resolve this issue during our contractor's review, by using the names of the individual Owner's Group.
The OG will l
. October 25, 1993 provide marked up page changes in the next several weeks to the NRC to correct these editorial errors.
We reviewed the status of generic change packages received at the July meeting.
This status is reflected in the updated status list provided in.
The OG provided the NRC with several new proposed' generic change packages (0 pen Items, Enclosure 5) for review in addition to several revisions to earlier packages.
They are: BWR-12 (E-bar), W0G-28 (accumulator), BWR-08 R.1 (inverter), WOG-13 R.1 (battery terminals), BWR-07 C.1 R.1 (bases consistency) and BWR-06 (PWR OPDRVs).
Packages approved at the August OG/0TSB mi.-ting were WOG-02 C.8, NRC-02 C.1, WOG-20 C.1, C.2, C.3, WOG-27 C.1, WOG-18 C.1, WOG-13 R.1, WOG-28, BWR-08 R.1, and BWOG-06 (accepted with comments).
We reviewed the status of the STS Action items and appropriate changes are reflected in the enclosed update (Enclosure 6).
The following items were discussed: Item # 60 The generic change of WOG 15 C.1, Steam Generator Tube Surveillance Program, was rejected by the NRC on June 29, 1993; however, the OG appealed it_to Bill Russell on August 12, 1993, and they will provide a new proposal. We discussed item # 124, Clarification for LC0 3.0.4. which SRXB reviewed and approved.
However, an OTSB staff member identified a case (LTOP operability) where the OG proposal would present a problem.
The OG will amend the proposal by identifying all the excepted circumstances. On item # 125, ISI/IST for snubbers, NRC will provide justification for the Traveler NRC-08>>.
And on item # 127, OG stated that the Operation with a Potential to Drain the Reactor Vessel (0PDRV) concern is not applicable to the PWR design and has submitted a Traveler proposing the deletion of requirements related to the concern.
The lead plant representatives discussed implementation status as follows:
Submittal NRC Review Implementation SONGS 11/93 6-9 months 1 year HATCH 11/93 6 months 3/95 ZION 1/95-3/95 unknown unknown BWR/6 10/93 9 months Grand Gulf: 1/95-3/95 Clinton:
4/95-6/95 Perry:
4/95-6/95 River Bend: 10/95-12/95
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-} October 25, 1993
[
Future meetings are scheduled as follows: September 22-23, 1993,- Irvine, CA and October 20-21, 1993, New Orleans, LA. There will be no meeting in November 1993.
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L Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR
Enclosures:
As stated cc w/o enclosures:
cc w/ enclosures:
T. Murley W. Hall, NUMARC W. Russell L. Bush, OG J. Partlow I
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. MEETING ATTENDEES' August 26 & 27, 1993 Attendee Orcanization Ray Baker SNC/BWROG Tom Porter TVA/WBN Darrell Gardner TVA/ Watts.Bar Blair Wunderly
.FPC/BWOG Sheri Mahoney Entergy/Bwrog Donald R. Hoffman EXCEL /BWROG/CE0G Lee Bush Ceco Sharon Mahler Hatch Jim Andrachek Westinghouse Marty Bryan ENERCON
]
Les England GSU/BWROG Chair.
Jim.Eaton NUMARC-John Vorees TVA/WBN Angela Chu NRC/0TSB Ronnie to NRC/0TSB e
C. 1. Grimes NRC/0TSB I
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i ENCLOSURE 2 l
AGENDA NRC/ INDUSTRY LEAD PLANT MEETING ~
AUGUST 26-27,-1993 ATLANTA, GA
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1.
Shutdown Risk Issues and Technical Specifications Status
- 2.. NUREG/ Bulletin Updates
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4.0/5.0 Status Update-1 4.
PTLR Status Update 5.
Steam Generator Tube Surveillance Program I
6.
NRC/ Industry Process and Administrative Issues 7.
Generic Changes (Travelers) 8.
Action Items List 9.
Implementation Status t
- 10. Future Meetings
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wassincTow, o.c. 20sss-oooi August 27, 1993 NOTE TO:
J. T. Wiggins, DE A. C. Thadani, DSSA i
B. A. Boger, DRCH F. J. Congel, DRSS FROM:
B. K. Grimes, DDRS
SUBJECT:
CONTENT OF TECHNICAL SPECIFICATION ADMINISTRATIVE CONTROLS The scope of administrative controls in technical specifications continues to be an issue related to regulatory improvements and will likely come up in rulemaking. Mr. Russell has proposed that the staff review the contents of the improved STS to determine where unnecessary details can be removed, or otherwise changed to reflect contemporary regulatory practices.
Consequently, Mr. Russell requested that we present this issue at his staff meeting on Monday, August 30, 1993.
The objectives of this review effort will be to determine the extent to which details in the administrative controls may be covered by other regulatory requirements (e.g., new or existing regulations or the QA plan)..The contents of these sections may, therefore, be justified by one of the following categories:
(1) requirements that are not covered by other regulatory requirements, but are necessary to assure safe operation of the facility, or.
(2) requirements that are covered by other regulatory requirements, but specific details need to be highlighted in the technical specifications because of the particular importance to the safe operation of the facility.
Other requirements in the administrative controls not in these categories should be removed from these sections. is a listing of the contents of the administrative controls in Revision 0 of the improved standard technical specifications (NUREG-1430 through 1434). The list has been annotated with the technical review branch that appears to have the primary responsibility for the contents of that section. Attachment 2 is the text of those sections from Rev 0 of NUREG-1430 (the B&W improved STS). This material is presented as background for the meeting on Monday.
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. August 27, 1993-We plan a series of status meetings in W. Russell's office the week of September 6,1993. to make final decisionc. on each section.
- Brian K. Grimes, Director Division of Operating Reactor Support cc:
W. Russell J. Partlow e
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' coa r.EM /u % - tyJ u SECTION S_UBJECT Cer/TE M M Y[.Y N 74%
5.0 ADMINISTRATIVE CONTROLS i
5.1 Responsibility HHFB t
5.2 Organization HHFB 5.2.1 Onsite and Offsite Organizations 5.2.2 Unit Staff (Minimum Shift Crew Composition) 5.3 Unit Staff Qualifications HHFB 5.4 Training HHFB f
5.5 Reviews and Audits RPEB
[
t 5.5.1 Plant Reviews RPEB
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5.5.1.1 Functions 5.5.1.2 Responsibilities 5.5.2
[0ffsite] Review and Audit RPEB 5.5.2.1 Functions 5.5.2.2
[0ffsite] Review Responsibilities 5.5.2.3 Audit Respensibilities 5.5.2.4
[ Technical) Review Responsibilities 5.5.3 Records RPEB 5.6 Technical Specifications (TS) Bases Control OTSB) 5.7 Procedures, Programs, and Manuals 5.7.1 Procedures 5.7.1.1 Scope
- a. Regulatory Guide 1.33 RPEB
- b. Emergency Operating Procedures [GL 82-33]
PEPB
- c. Security pl:n implement:tica PSGB
-d. Emcrgency plan impicm:ntati;n PEPB
- e. QA for effluent and environmental monitoring PRPB-
- f. Fire Protection Program implementation SPLB i
- g. All programs specified in Specification 5.7.2.
5.7.1.2 Review and Approval RPEB 5.7.1.3 Temporary Changes RPEB 5.'7.2 Programs and Manuals 5.7.2.1 Radiation Protection Program PRPB r
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'E?rW.!$,'?U 5.7.2.2 Process Control Program (PCP)
PRPB 5.7.2.3 Offsite Dose Calculation Manual (ODCM)
PRPB 5.7.2.4 Primary Coolant Sources Outside Containment PRPB 5.7.2.5 In Plant Radiation Monitoring PRPB 5.7.2.6 Post Accident Sampling PRPB/EMCB 5.7.2.7 Radioactive Effluent Controls Program PRPB 5.7.2.8 Radiological Environmental Monitoring Program PRPB 5.7.2.9 Component Cyclic or Transient Limit SPLB 5.7.2.10
[ Pre-Stressed Containment Tendon Surveillance K wS Program]
5.7.2.11 Inservice Inspection Program EM ' '
EMEBP m
5.7.2.12 Inservice Testing Program 5.7.2.13 Steam Generator Tube Surveillance Program EMCB%tM 5.7.2.14 Secondary Water Chemistry EMCB 5.7.2.15 Ventilation Filter Testing Program (VFTP)
EMCB 5.7.2.16 Explosive Gas and Storage Tank Radioactivity EMCB/SCSB Monitoring Program 5.7.2.17 Diesel Fuel Oil Testing Program EMCB 5.7.2.18 Fire Protection Program SPLB 5.B Safety Function Determination Program (SFDP)
OTSB?
5.9 Reporting Requirements 5.9.1 Routine Reports 5.9.1.1 Startup Report SRXB 5.9.1.2 Annual Reports
- a. Occupational Radiation Exposure Report PRPB
- b. [Any other unit unique Annual reports]
5.9.1.3 Annual Radiological Environmental Operating Report PRPB 5.9.1.4 Radioactive Effluent Release Report PRPB 5.9.1.5 Monthly Operating Reports SRXB/0EAB 5.9.1.6 CORE OPERATING LIMITS REPORT (COLR)
SRXB 5.9.1.7 PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
EMCB 5.9.2 Special Reports
- a. ECCS Actuations SCSB/SPLB/0EAB
- b. EDG Failures EELB/SPLB/0EAB
- d. Containment Tendon Surveillance Program Failures SCSB
- e. Plugged Steam Generator Tubes EMCB 5.10 Record Retention RPEB l 5.11
[High Radiation Area]
PRPB p,< 2 4 2._
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'Respsnsibility 1
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5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility
-T 5.1.1 The [ Plant Superintendent] shall be responsible' for overall unit operation and shall delegate in writing the succession to this-i responsibility during his absence.
The:[ Plant Superintendent], or his designee, in accordance.with approved administrative procedures,'shall approve prior.to implementation, each proposed test or experiment and proposed changes and modifications to unit systems or equipment that affect nuclear safety.
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5.1.2 The [ Shift Supervisor (SS)] shall; be responsible for the control.
room command: function.
A. management directive to this effect, signed by the [ highest level of corporate or site management]
shall be issued annually to all station' personnel. During any absence of the [SS] from the control room while the unit is-in MODE 1, 2, 3, or 4, an individual with a valid Senior Reactor Operator. (SRO) license shall be designated to assume the control j
room command function. During any absence of the [SS] from the-e control room while the unit is in MODE 5 or 6, an individual with-a valid SRO license or Reactor Operator license.shall be -
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designated to assume the. control room command function.
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BWOG-STS 5.0-1 Rev.
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Organizati n-5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 9
5.2.1 Onsite and Offsite Orcanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
a.
Linas of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the [FSAR];
b.
The [ Plant Superintendent) shall be responsible for overall i
safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant; c.
The [a specified corporate executive position) shall have '
corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and j
d.
The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may l
report to the appropriate onsite manager; however, these t
individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Unit Staff The unit staff organization shall be as follows:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 5.2.2-1.
i (continued)
BWOG STS 5.0-2 Rev.
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Organizaticn
.5.2 5.2 Organization 5.2.2 Unit Staff (continued) b.
At least one licensed Reactor Operator (RO) shall be present in the control-room when fuel is in the reactor.
In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
c.
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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
d.
Either a licensed SRO or licensed SRO limited to fuel handling who has no concurrent responsibilities during this operation shall be present during fuel handling and shall i
directly supervise all CORE ALTERATIONS.
e.
Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g., licensed SR0s, licensed R0s, hr physicists, auxiliary operators, and key maintenance personnel).
Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work an [8 or 12] hour day, nominal 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time; 2.
An individual should not be permitted to work more than
[
16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hovr period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time; 3.
A break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be &llowed between work periods, including shift turnover time; (continued) i BWOG STS 5.0-3 Rev. O,09/28/92
t Organization j
5.2
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5.2 Organization 5.2.2 Unit Staff (continued) i 4.
Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.
Any deviation from the above guidelines shall be authorized in advance by the [ Plant Superintendent] or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established i
4 procedures and with documentation of the basis for granting the deviation.
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 I
hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
l The amount of overtime worked by unit staff members i
performing safety related functions shall be limited and controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).
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The'[0perations Manager or Assistant Operations Manager]
shall hold an SRO license.
l g.
The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant i
analysis with regard to the safe operation of the unit.
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O,09/28/92
' Organization 5.2 Table 5.2.2-1 (page 1 of 1)
Minimum Shift Crew Composition (a)
[ Single Unit Facility]
POSITION (b)
HINIMUM CREW NUMBER UNIT IN MODE UNIT IN MODE 1, 2, 3, 0R 4 5 OR 6 SS 1
1 SR0 1
None R0 2
1 A0 (c) 2 1
STA 1
None (a) The shift crew composition may be one less than the minimum requirements of Table 5.2.2-1 for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to accommodate unexpected absences of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements of Table 5.2.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
(b) Table Notation:
- [ Shift Supervisor] with a Senior Reactor Operator license; SR0 - Individual with a Senior Reactor Operator license; RO
- Individual with a Reactor Operator license; A0
- Auxiliary Operator; STA - Shift Technical Advisor.
(c) The STA position may be filled by an on-shift SS or SRO provided the individual meets the Commission Policy Statement on Engineering Expertise on Shift.
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BWOG STS 5.0-5 Rev.
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-1 Tabic 5.2.2-1 (page 1 of 1) l Minlan Shif t Crew Composition (e)
ITwo Units With a Consnan control Roond (Totals for Both Units) i POSITION (b)
MINIMUM CREW NUMBER ONE UNIT IN MCDE 1, 2, 3, OR 4, AND ONE UNIT EACH UNIT IN MODE 1, 2, IN MODE 5, MODE 6, OR EACH tm!T IN MODE 5 OR 3, OR 4
1 1
h SRO 1
1 None
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3 2
i AD 3
3 3
ICI STA 1
1 None f
I (a)
The shif t crew conposition may be one less than the miniaan requirements of Table 5.2.21 for not l
acre than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to acconsmodate mexpected absence of on-duty shif t crew menbers, provided insnediate action is taken to restore the shif t crew conposition to within the mininun requirements of f
Table 5.2.2-1.
This provision does not permit any shift crew position to be unmanned upon shift change due to en oncoming shift crewman being late or absent.
(b)
Table Notation:
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[shif t Servisor) with a senior Reactor Operator license for each unit whose reactor contains Ji 55 fuel.
i SRO - Individual with a Senior Reactor Operator license for each unit whose reactor contains fuel.
i Otherwise, provide en individual for each unit who holds a Senior Reactor Operator license for the unit assigned. During CORE ALTERATIONS on either unit at least one licensed SRO or licensed SR0 tiaited to fuel handling, who has no other concurrent responsibilities, must be-f present.
i R0 - Individual with a Reactor Operator license or a senior Reactor Operator license for unit assigned. At least one RO shall be assigned to each unit whose reacto* contains fuel and one -
R0 shall be assigned as relief operator for mit(s) in. MODE 1, 2, or 3.
Indivichats acting as relief operators shall hold a license for both units. Otherwise, for each unit, provide a relief operator who holds a license for the unit assigned.
AO - At least one auxiliary operator shall be assigned to each mit tAose reactor contains fuel.
STA - Shif t Technical Advisor.
i (c)
The STA position may be fitted ty en on-shif t SS or $RO provided the irdividual meets the Conseission Policy Statement on Engineering Expertise on shift.
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s Organization 5.2 Table 5.2.2-1 (page 1 of 1)
Minimum Shift Crew Composition (a)
[Two Units With Two Control Rooms]
(Numbers for Each Unit)
POSITION (b)
MINIMUM CREW NUMBER UNIT IN MODE UNIT IN MODE 1, 2, 3, OR 5 OR 6; OTHER 4; OTHER UNIT UNIT IN MODE UNIT IN MODE UNIT IN MODE IN MODE 5 OR 5 OR 6 OR 1, 2, 3, OR 4 5 OR 6 6 OR DEFUELED DEFUELED SS 1(d) 1(d)
}(d) 1(d)
SR0 1
None 1
None R0 2
1 2
1(e)
A0 (C) 2(d) 1 2
2 STA 1
None 1
None (a) The shift crew composition may be one less than the minimum requirements of Table 5.2.2-1 for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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 of Table 5.2.2-1.
This provision does not permit ~
any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.
(b) Table Notation:
- [ Shift Supervisor] with a Senior Reactor Operator license; SRO - Individual with a Senior Reactor Operator license; R0
- Individual with a Reactor Operator license; A0
- Auxiliary Operator; STA - Shift Technical Advisor.
(c) The STA position may be filled by an on-shift SS ce SR0 provided the individual meets the Commission Policy Statement on Engineering Expertise on Shift.
(d)
Individual may fill the same position on the other unit if licensed for i
- both, s
(e) One of the two required individuals may fill the same position on the other unit.
i BWOG STS 5.0-7 Rev.
O, 09/28/92 t
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i 5.0. ADMINISTRATIVE CONTROLS i
5.3 - Unit Staff. Qualification.= -
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Minimum qualifications for members of'th'e unit' staff shall Reviewer's Note:
.t be specified by-use of an overall qualification staterent 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.
i
.t 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 mo're l
recent revisions, or ANSI Standard acceptable to the'NRC staff].
The staff not' covered by [ Regulatory Guide 1.8] shall' meet or i
exceed the minimum qualifications of [ Regulations,. Regulatory l
Guides, or ANSI Standards acceptable to NRC staff].. In addition, the Shift Technical Advisor shall meet the qualifications i'
specified by the Commission Policy Statement on Engineering-Expertise on Shift.
I i
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q
'I BWOG STS 5.0-8 Rev.
O, 09/28/92
-l
Training t
5.4 5.0 ADMINISTRATIVE CONTROLS i
5.4 Training 5.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the [ position title) and shall meet or exceed the requirements and recommendations of Section [
] of [an ANSI Standard acceptable to the NRC staff] and 10 CFR 55, and, for appropriate designated positions, shall j
include familiarization with relevant industry operational experience.
l I
I i
i i
BWOG STS 5.0-9 Rev.
O, 09/28/92 i
Reviews and Audits 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Reviews and Audits Reviewer's Note: The licensee shall describe the method (s) established to conduct independent reviews and audits. The methods may take a range of forms acceptable to the NRC. These methods may include creating an organizational unit or a standing or ad hoc committee, or assigning individuals capable of conducting these reviews and audits. When an individual performs a review function, a cross disciplinary review determination is necessary.
If deemed necessary, such reviews shall be performed by the review personnel of the appropriate discipline.
Individual reviewers shall not review their own work.
Regardless of the method used, the licensee shall specify the functions, organizational arrangement, responsibilities, appropriate ANSI /ANS 3.1-1981 qualifications, and reporting requirements of each functional element or unit that contributes to these processes.
Reviews and audits of activities affecting plant safety have two distinct elements. The first element is the reviews performed by plant staff personnel to ensure that day to day activities are conducted in a safe manner. These reviews are described in Section 5.5.1.
The second element, described in Section 5.5.2, is the [offsite] reviews and audits of unit activities and programs affecting nuclear safety that are performed independent of the plant staff. The [offsite] reviews and audits should provide integration of the reviews and audits into a cohesive program that provides senior level utility management with an assessment of facility operation and recommends actions to improve nuclear safety and plant reliability.
It should include an assessment
_of the effectiveness of reviews conducted according to Section 5.5.1.
5.5.1 Plant Reviews Reviewer's Note:
The licensee shall describe provisions for plant reviews (organization, reporting, records) and the appropriate
_ ANSI /ANS Standard for personnel qualification.
5.5.1.1 Functions The [ plant review method specified in Specification 5.5.1) shall, as a minimum, incorporate functions that:
a.
Advise the [ Plant Superintendent] on all matters related to nuclear safety; (continued)
BWOG STS 5.0-10 Rev.
O, 09/28/92
Reviews and Audits i
5.5 5.5 Reviews and Audits
- r 5.5.1.1 Functions (continued) i b.
Recommend to the [ Plant Superintendent] approval or disapproval of items considered under Specifications 5.5.1.2.a through 5.5.1.2.e prior to their implementation, except as provided in Specification 5.7.1.3; c.
Determine whether each item considered under Specifications L
5.5.1.2.a through 5.5.1.2.d constitutes an unreviewed safety question as defined in 10 CFR 50.59; and d.
Notify the [Vice President--Nuclear Operations) of any safety significant disagreement between the [ review organization or individual specified in Specification 5.5.1] and the [ Plant Superintendent] within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, the [ Plant Superintendent] shall have responsibility for resolution of i
such disagreements pursuant to Specification 5.1.1.
I 5.5.1.2 Responsibilities The [ plant review method specified in Specification 5.5.1) shall be used to conduct, as a minimum, reviews of the following:
a.
All proposed procedures required by Specification 5.7.1.1 and changes thereto; b.
All proposed programs required by Specification 5.7.2 and changes thereto; c.
All proposed changes and modifications to unit systems or equipment that affect nuclear safety; 1
d.
All proposed tests and experiments that affect nuclear l
safety; and e.
All proposed changes to these Technical Specifications (TS),
their Bases, and the Operating License.
1 i
(continued)
BWOG STS 5.0-11 Rev.
O, 09/28/92 l
Reviews and Audits 5.5 5.5 Reviews and Audits (continued) 5.5.2 I0ffsitel Review and Audit i
Reviewer's Note: The licensee shall describe the provisions for reviews and audits independent of the plant's staff (organization, reporting, and records) and the appropriate ANSI /ANS Standards for personnel qualifications. These individuals may be located onsite or offsite provided organizational independence from plant staff is maintained. The [ technical] review responsibilities, Specification 5.5.2.4, shall include several individuals located onsite.
5.5.2.1 Functions The [offsite review and audit provisions specified in Specification 5.5.2) shall, as a minimum, incorporate the following functions that:
a.
Advise the [Vice President--Nuclear Operations) on all matters related to nuclear safety; b.
Advise the management of the audited organization, and [its Corporate Management and Vice President--Nuclear Operations],
of the audit results as they relate to nuclear safety; c.
Recommend to the management of the audited organization, and its management, any corrective action to improve nuclear safety and plant operation; and d.
Notify the [Vice President--Nuclear Operations) of any safety significant disagreement between the [ review organization or individual specified in Specification 5.5.2] and the
[ organization or function being reviewed] within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.5.2.2
[0ffsite] Review Responsibilities The [ review method specified in Specification 5.5.2] shall be responsible for the review of:
a.
The safety evaluations for changes to procedures, equipment, or systems, and tests or experiments completed under the provisions of 10 CFR 50.59, to verify that such actions do not constitute an unreviewed safety question as defined in 10 CFR 50. Q; i
(continued) i f
BWOG STS 5.0-12 Rev.
O, 09/28/92 l
l
q
+
Reviews and Audits-
-- 5.5-
'i 1,
1 5.5 LReviews and Audits i
5.5.2.2
[0ffsite] Review Responsibilities.(continued)
-j b.
Proposed. changes to' procedures, equipment, or systems-that involve an unreviewed safety question ~as defined-in--
.i 10 CFR 50.59; i
c.
Proposed tests or experiments that involve an unreviewed safety question as defined in 10 CFR 50.59-q d.
Proposed changes to TS and the Operating License; j
e.
Violations of codes, regulations, orders, license i
requirements, and internal. procedures or instructicns having' l
nuclear safety significance; f.
All Licensee Event Reports required by 10 CFR 50.73; j
g.
Plant staff performance; t
h.
Indications of unanticipated deficiencies in any. aspect'of-design or operation of structures, systems, or components that could affect nuclear safety; l
1.
Significant accidental, unplanned, or uncontrolled 4
radioactive releases, including corrective action to' prevent recurrence
~
J.
Significant' operating abnormalities or deviations from j
normal and expected performance of equipment that-affect' nuclear safety; and-
- i k.
The performance of the corrective action system.
-l Reports or records of these reviews shall be forwarded to the l
[Vice President-Nuclear Operations) within 30 days following completion of the review.
5.5.2.3 Audit Responsibilities q
The audit responsibilities shall encompass:
a.
The conformance of unit operation to provisions contained l
within the TS and applicable license conditions; i
b.
The training and qualifications of the unit staff; I
7 (continued)
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j BWOG STS 5.0-13 Rev.
0, 09/28/92 l
1 I
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U N-Reviews and'Auditsi 5.5-5.5 Reviews and Audits 5.5.2.3 Audit Responsibilities (continued) a-c.
The implementation of, all programs required by Specification 5.7.2; d.
Actions taken to correct deficiencies occurring in equipment, structures, systems, components, or method of operation that affect nuclear safety; and e.
Other activities and documents as requested by the [Vice President-Nuclear Opera.tions].
Reports or records of these. audits shall be forwarded to the [Vice President-Nuclear Operations] within 30 days following completion' of the review.
5.5.2.4
[ Technical] Review Responsibilities The [ technical] review responsibilities shall encompass:
a.
Plant operating characteristics, NRC-issuances, industry-advisories, Licensee Event Reports, and other sources that may indicate areas for improving plant safety; b.
Plant operations, modifications, maintenance, and surveillance to verify independently that these activities-are performed safely and correctly and that human errors are reduced as much as practical; c.
Internal and external operational experience information that may indicate areas for-improving plant safety; and.
d.
Making detailed. recommendations through the-[Vice President-Nuclear Operations) for revising procedures, equipment modifications or other means of improving nuclear safety and plant reliability.
5.5.3 Records Written records of reviews and audits shall be maintained. As a minimum these records shall include:
y a.
Results of the activities conducted under the provisions of-Section 5.5; (continued)
.BWOG STS 5.0-14 Rev.
O, 09/28/92
Reviews and Audits 5.5 5.5 Reviews and Audits 5.5.3 Records (continued) b.
Recommendations to the management of the organization being audited; c.
An assessment of the safety significance of the review or audit findings; d.
Recommended approval or disapproval of items considered under Specifications 5.5.1.2.a through 5.5.1.2.e; and e.
Determination whether each item considered under Specifications 5.5.1.2.a through 5.5.1.2.d constitutes an unreviewed safety question as defined in 10 CFR 50.59.
BWOG STS 5.0-15 Rev.
O, 09/28/92 l
l l
TS Bases Centrol-5.6 5.0 ADMINISTRATIVE CONTROLS
-5.6 Technical ~ Specifications (TS) Bases Control 5.6.1 Changes to the Bases of the TS shall be made under appropriate administrative controls and reviewed according to Specification 5.5.1.
5.6.2 Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:
a.
A change in the TS incorporated in the license; or b.
A change to the updated FSAR or Bases that involves an unreviewed safety question as defined in 10 CFR 50.59.
5.6.3 The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR.
4 5.6.4 Proposed changes that meet the criteria of (a) or (b) above shall l
be reviewed and approved by the NRC prior to implementation.
i Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with-10 CFR 50.71.
BWOG STS 5.0-16 Rev.
O, 09/28/92
a Procedures, Prograns, and Mar.zds 5.7 i
5.0 ADMINISTRATIVE CONTROLS 5.7 Procedures, Programs, and Manuals 5.7.1 Procedures 5.7.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:
a.
The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978; b.
The emergency operating procedures required to implement the requirements of NUREG-0737 and to NUREG-0737, Supplement 1, l
as stated in [ Generic Letter 82-33];
l c.
Security plan implementation; d.
Emergency plan implementation; e.
Quality assurance for effluent and environmental monitoring; f.
Fire Protection Program implementation; and g.
All programs specified in Specification 5.7.2.
5.7.1.2 Review and Approval Each procedure of Specification 5.7.1.1, and changes thereto, shall be reviewed in accordance with Specification 5.5.1, approved by the [ Plant Superintendent] or his designee in accordance with i
approved administrative procedures prior to implementation and l
reviewed periodically as set forth in administrative procedures.
5.7.1.3 Temporary Changes I
Temporary changes to procedures of Specification 5.7.1 may be made provided:
a.
The intent of the existing procedure is not altered; b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior i
Reactor Operator license on the unit affected; and l
(continued)
]
BWOG STS 5.0-17 Rev.
O, 09/28/92 l
l-4 l
1,
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Proccdures, Pr: grams,- and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.1.3 Temporary Changes (continued)
J c.
The change is documented and reviewed in accordance with Specification 5.5.1 and approved by the [ Plant Superintendent] or his designee in accordance with approved-administrative procedures within 14 days of implementation.
5.7.2 Procrams and Manuals The following programs shall be established, implemented, and maintained.
5.7.2.1 Radiation Protection Program Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
l 5.7.2.2 Process Control Program (PCP)
The PCP shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes will be accomplished to ensure compliance with 10 CFR 20, 10 CFR 61, and 10 CFR 71; state regulations; burial ground requirements; and other requirements governing the disposal of solid radioactive waste.
Licensee initiated changes to the PCP:
l a.
Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
1.
Sufficient information to support the change (s) and appropriate analyses or evaluations justifying the change (s),and 2.
A determination that the change (s) maintain the overall conformance of the solidified waste product to the existing requirements of Federal, State, or other applicable regulations.
(continued)
BWOG STS 5.0-18 Rev.
O, 09/28/92
Procedures, Prrgrams, and Manuals 5.7 5.7 Procedures, Programs, and Manuals-5.7.2.2 Process Control Program (PCP)
(continued) b.
Shall be effective after review and acceptance by the
[ review method of Specification 5.5.1] and the approval of the [ Plant Superintendent].
5.7.2.3 Offsite Dose Calculation Manual (ODCM) a.
The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program; and b.
The ODCM shall also contain the Radioactive Effluent Controls and Radiological Environmental Monitoring programs required by Specification 5.7.2, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification [5.9.1.3]
and Specification [5.9.1.4].
Licensee initiated changes to the ODCH:
a.
Shall be documented and records of reviews performed shall be retained. This documentation shall contain:
1.
sufficient information to. support the change (s) together with the appropriate analyses or evaluations justifying the change (s), and 2.
a determination that the change (s) maintain the levels of radioactive efflu it control required by '
10 CFR 20.106, 40 t < 190,10 CFR 50.36a, and 10 CFR 50, Appendix 1, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations; b.
Shall become effective after review and accepjance by the
[ review method of Specification 5.5.1] and the approval of the [ Plant Superintendent]; and (continued)
BWOG STS 5.0-19 Rev.
O, 09/28/92
Procedures, Program, and Manuals 5.7 5.7 Procedures, Programs, and Manuals t
5.7.2.3 Offsite Dose Calculation Manual (ODCM)
(continued) c.
Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in'which any change in the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.
5.7.2.4 Primary Coolant Sources Outside Containment f
This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include [ Low Pressure Injection, Reactor Building Spray, Makeup and Purification, and Hydrogen Recombiner]. The program shall include the following:
a.
Preventive maintenance and periodic visual inspection L
requirements; and b.
Integrated leak test requirements for each system at refueling cycle intervals or less.
5.7.2.5 In Plant Radiation Monitoring This program provides controls to ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:
a.
Training of personnel; b.
Procedures for monitoring; and c.
Provisions for maintenance of sampling and analysis equipment.
5.7.2.6 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and (continued)
BWOG STS 5.0-20 Rev.
O, 09/28/92
Procedures, Programs, and Manuals 5.7-5.7 Procedures, Programs, and Manuals 5.7.2.6 Post' Accident Sampling (continued)
{
particulates ir. plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:
a.
Training of personnel; b.
Procedures for sampling and analysis; and c.
Provisions for maintenance of sampling and analysis equipment.
5.7.2.7 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of 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 ir.clude 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 10 CFR 20, Appendix B,- Table II, Column 2; c.
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with th; 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 cn.nulative and projected dose contributions from radioactive t/fluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCH at least every 31 days; (continued)
BWOG STS 5.0-21 Rev.
O, 09/28/92
Procedures, Programs, and Manuals 5.7 5.7. Procedures, Programs, and Manuals 5.7.2.7 Radioactive Effluent Controls Program (continued) 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 1; g.
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1; 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 r
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 frW cycle sources, conforming to 40 CFR 190.
5.7.2.8 Radiological Environmental Monitoring Program This program is for monitoring the radiation and radionuclides in the environs of the plant. The program shall provide representative measurements of radioactivity in the highest potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall be contained in the ODCM, shall conform to the guidance of 10 CFR 50, Appendix I, and 'shall include the following:
a.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM; (continued)
BWOG STS 5.0-22 Rev.
O, 09/28/92
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.8 Radiological Environmental Monitoring Program (continued)
I b.
A Land Use Census to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census; and c.
Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as-part of the quality assurance program for environmental monitoring.
5.7.2.9 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.
5.7.2.10 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.
5.7.2.11 Inservice Inspection Program This program provides controls for inservice inspection of ASME Code Class 1, 2, and 3 components, including applicable supports.
The program shall include the following:
a.
Provisions that inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a; i
(continued)
BWOG STS 5.0-23 Rev.
O, 09/28/92 i
i Proc:dures~, Progra s, and Manuals 5.7 i
5.7 Procedures, Programs, and Manuals 5.7.2.11 Inservice Inspection Program (continued) b.
The provisions of SR 3.0.2 are applicable to the frequencies for performing inservice inspection activities; c.
Inspection of each reactor coolant pump flywheel per the recommendation of Regulation Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975; and d.
Nothing i.n the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.
5.7.2.12 Inservice Testing Program j
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:
a.
Provisions that inservice testing of ASME Code Class 1, 2, and 3 pumps, valves, and snubbers shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by i
10 CFR 50.55a; b.
Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:
ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for Required Frequencies i
inservice testing for performing inservice activities testino activities t
Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days (continued)
BWOG STS 5.0-24 Rev.
O, 09/28/92
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.12 Inservice Testing Program (continued) c.
The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities; d.
The provisions of SR 3.0.3 are applicable to inservice testing activities; and e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be.
construed to supersede the requirements of any TS.
5.7.2.13 Steam Generator (SG) Tube Surveillance Program Each SG shall be demonstrated OPERABLE by performance of an inservice inspection program. The program shall include the following:
a.
SG tube sample size selection, sample size expansion, and inspection result classification criteria. Sample selection and testing shall be in accordance with [ Regulatory Guide 1.83, Revision [ ], date),
b.
The establishment of SG tube inspection frequency dependent upon inspection result classification.
Inspection. frequency shall be in accordance with [ Regulatory Guide 1.83, Revision [ ], date).
c.
SG tube plugging / repair limits. These limits shall be [40]%
of the nominal tube wall thickness consistent with
[ Regulatory Guide 1.83, Revision [ ], date).
d.
Specific definitions and limits for SG tube inservice inspection acceptance criteria consistent with [ Regulatory Guide 1.83, Revision [ ], date].
The content and frequency of written reports shall be in accordance with Specification 5.9.2.
The provisions of SR 3.0.2 are applicable to SG Tube Surveillance Program inspection frequencies except those established by Category C-3 inspection results.
[ Key elements to be discussed and provided.]
(continued)
BWOG STS 5.0-25 Rev. O,09/28/92 t
w--
Procedures, Pr grams, and Manuals 5.7 i
5.7 Procedures, Programs, and Manuals 5.7.2 Proarams and Manuals (continued) 5.7.2.14 Secondary Water Chemistry This program provides controls for monitoring secondary water chemistry to inhibit SG tube degradation and low pressure turbine disc stress corrosion cracking. The program shall include:
a.
Identification of a sampling schedule for the critical variables and control points for these variables; b.
Identification of the procedures used to measure the values of the critical variables; c.
Identification of process sampling points, which shall include monitoring the discharge of the condensate pumps for evidence of condenser in leakage; d.
Procedures for the recording and management of data; e.
Procedures defining corrective actions for all off control point chemistry conditions; and f.
A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.
5.7.2.15 Ventilation Filter Testing Program (VFTP)
A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in [ Regulatory Guide
],
and in accordance with [ Regulatory Guide 1.52, Revision 2, ASME -
N510-1989, and AG-1].
a.
Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < [0.05%)-when tested in accordance with [ Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below [i 10%).
(continued)
BWOG STS 5.0-26 Rev.
O, 09/28/92
^
Procedures, Progra s, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.15 Ventilation Filter Testing Program (VFTP)
(continued)
ESF Ventilation System Floerate b.
Demonstrate for e ch of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < [0.5]% when tested in accordance with [ Regulatory Guide 1.52, Revision 2, and ASME H510-1989] at the system flowrate specified below [i 10%).
ESF Ventilation System Flowrate F
c.
Demonstrate for each of the ESF systems that a laboratory, test of a sample of the charcoal adsorber, when obtained as described in [ Regulatory Guide 1.52, Revision 2], shows the methyl iodide penetration less than the value specified below when tested in accordance with [ ASTM D3803-1989] at a temperature of s [30*C] and greater than or equal to the relative humidity specified below.
ESF Ventilation System Penetration RH Reviewer's Note: Allowable penetration - [100% - methyl iodide efficiency for charcoal credited in staff safety evaluation]/
(safety factor).
Safety factor - [5] for systems with heaters.
[7] for systems without heaters.
(continued)
BWOG STS 5.0-27 Rev.
O, 09/28/92
Prccedures, Prcgrams, and Manuals 5.7 i
5.7 Procedures, Programs, and Manuals 5.7.2.15 Ventilation Filter Testing Program (VFTP)
(continued) d.
Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the pref 11ters, and the charcoal adsorbers is less than the value specified below when tested in accordance with [ Regulatory Guide 1.52, Revision 2, and ASME N510-1989] at the system flowrate specified below [f 10%).
ESF Ventilation System Delta P Flowrate e.
Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [i 10%) when tested in
__accordance with [ASME N510-1989].
ESF Ventilation System Wattage The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
5.7.2.16 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the (Waste Gas Holdup System], [the quantity of radioactivity contained in gas storage tanks or fed into the offgas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks). The gaseous radioactivity quantities shall be determined following the methodology in (Branch Technical Position (BTP) ETSB 11-5,
" Postulated Radioactive Release due to Waste Gas System Leak or Failure"). The liquid radwaste quantities shall be determined in accordance with [ Standard Review Plan, Section 15.7.3, " Postulated Radioactive Release due to Tank Failures"].
(continued)
BWOG STS 5.0-28 Rev.
O, 09/28/92 7
h
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.16 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)
The program shall include:
a.
The limits for concentrations of hydrogen and oxygen in the
[ Waste Gas Holdup System] and a surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion).
b.
A surveillance program to ensure that the quantity of radioactivity contained in [each gas storage tank and fed into the offgas treatment system] is less than the amount that would result in a whole body exposure of 2 0.5 re.n to any individual in an unrestricted area, in the event of (an uncontrolled release of the tanks' contents].
c.
A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the (Liquid Radwaste Treatment System] is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B. Table II, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
5.7.2.17 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:
(continued)
BWOG STS 5.0-29 Rev.
O, 09/28/92 I
Procedures, Programs, and Manuals 5.7 5.7 Procedures, Programs, and Manuals 5.7.2.17 Diesel Feel Oil Testing Program (continued) a.
Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:
1.
an API gravity or an absolute specific gravity within
- limits, 2.
a flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and 3.
a clear and bright appearance with proper color; b.
Other properties for ASTM 2D fuel oil are within limits within 30 days following sampling and addition to storage tanks; and c.
Total particulate concentration of the fuel oil is s 10 mg/l when tested every 31 days in accordance with ASTM D-2276, Method A-2 or A-3.
5.7.2.18 Fire Protection Program This program provides controls to ensure that appropriate fire protection measures are maintained to protect the plant from fire and to ensure the capability to achieve and maintain safe shutdown in the event of a fire is maintained.
BWOG STS 5.0-30 Rev.
O, 09/28/92
1 SFDP 5.8 5.0 ADMINISTRATIVE CONTROLS 5.8 _ Safety Function Determination Program (SFDP) 5.8.1 This program ensures loss of safety' function is detected and i
appropriate actions taken. Upon failure to meet two or more LCOs at the same time, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and l
corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LC0 3.0.6.
I 5.8.2 The SFDP shall contain the following:
t a.
Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected; b.
Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists; c.
Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and d.
Other appropriate limitations and remedial or compensatory actions.
5.8.3 A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed.
For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:
a.
A required system redundant to the system (s) supported by the inoperable support system is also inoperable (Case A);
l or b.
A required system redundant to the system (s) in turn supported by the inoperable supported system is also inoperable (Case B); or (continued) i BWOG STS 5.0-31 Rev.
O, 09/28/92 t
i
SFDP~
5.8 '
5.8 SFDP 5.8.3 (continued) f c.
A required system redundant to the support system (s) for the i
supported systems (a) and (b) above is also inoperable (Case C).
Generic Example:
l Train A Train B System i System i
.-Case C 1
1 System 11
.-(Support System System ii i
Inoperable) 1 System 111 System iii
-Case A 1
1 1
System iv System iv
-Case B 5.8.4 The SFDP identifies where a loss of safety function exists.
If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.
i f
i BWOG STS 5.0-32 Rev.
O, 09/28/92 t
I
R: porting R:quirements 5.9 5.0 ADMINISTRATIVE CONTROLS 5.9 Reporting Requirements 5.9.1 Routine Reports The following reports shall be submitted in accordance with 10 CFR 50.4.
5.9.1.1 Startup Report A summary report of plant startup and power escalation testing shall be submitted following:
a.
Receipt of an Operating License; b.
Amendment to the license involving a planned increase in power level; c.
Installation of fuel that has a different design or has been manufactured by a different fuel supplier; and d.
Modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
The initial Startup Report shall address each of the startup tests identified in FSAR, Chapter [14], and shall-include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any i
corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be included in this report.
Subsequent Startup Reports shall address startup tests that are necessary to dernonstrate the acceptability of changes and modifications.
Startup Reports shall be submitted within 90 days following completion of the Startup Test Program; 90 days-following resumption or commencement of commercial power operation; or 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of Startup Test Program, and resumption or commencement of commercial operation), supplementary reports shall be submitted at least every 3 months until all three events have been completed.
(continued)
BWOG STS 5.0-33 Rev.
O, 09/28/92
r Reporting Requirzments 5.9 5.9 Reporting Requirements 5.9.1 Eputine Reports (continued) 5.9.1.2 Annual Reports
NOTE--------------------------------
A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.
=--- _
- =_.
=---------
Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted by March 31 of each year.
[The initial report shall be submitted by March 31 of the year following initial criticality.]
Reports required on an annual basis _ inclute:
a.
Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) receiving exposures > 100 mrem /yr and their associated man rem exposure according to work and job functions (e.g.,
reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [ describe maintenance), waste processing, and refueling).- This tabulation supplements the requirements of 10 CFR 20.407.
The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements. Small exposures totalling < 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources should be assigned to specific major work functions; and
[b.
Any other unit unique reports required on an annual basis.]
i (continued)
BWOG STS 5.0-34 Rev.
O, 09/28/92
Reporting R:quir:ments 5.9 5.9 Reporting Requirements 5.9.1 Routine Reports (continued) 5.9.1.3 Annual Radiological Environmental Operating 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.
.=-.= -------- __
The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (0DCM), 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, i
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.
e (continued)
BWOG STS 5.0-35 Rev.
O, 09/28/92
R: porting Requir;ments
+
5.9 5.9 Reporting Requirements 5.9.1 Routine Reports (continued)
?
5.9.1.4 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 1
submittal shall specify the releases of radioactive material from each unit.
r The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accardance 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 ecnformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.I.
5.9.1 5 Honthly Operating Reports Routine reports of operating statistics and shutdown experience [,
including documentation of all challenges to the pressurizer power operated relief valves or pressurizer safety valves,] shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.
5.9.1.6 CORE OPERATING LIMITS REPORT (COLR) a.
Core operating limi'a 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 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:
(continued) 5 BWOG STS 5.0-36 Rev.
O, 09/28/92 t
4 Reporting Requirements 5.9 5.9 Reporting Requirements 5.9.1.6 CORE OPERATING LIMITS REPORT (COLR)
(continued)
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 t
_ 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 1
(ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
3 d.
The COLR, including any midcycle revisions or supplements, g
shall be provided upon issuance for each reload cycle to the NRC.
5.9.1.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)
RCS pressure and temperature limits, including heatup and cooldow' rates, criticality, and hydrostatic and leak test limits, shall be established and documented in the PTLR.
[The individual Specifications that address the reactor vessel pressure and temperature limits and the heatup and cooldown rates may be referenced.] The analytical methods used to determine the pressure and temperature limits including the heatup and cooldown rates shall be those previously reviewed and approved by the NRC in [ Topical Report (s), number, title, date, and NRC staff approval document, or staff SER for a plant specific methodology by NRC letter and date]. The reactor vessel pressure and temperature limits, including those for heatup and cooldown rates, shall be determined so that all applicable limits (e.g., heatup limits, cooldown limits, and inservice leak and hydrostatic testing limits) of the analysis are met. The PTLR, including revisions or L supplements thereto, shall be provided upon issuance for each
.i reactor vessel fluency period.
t (continued)
BWOG STS 5.0-37 Rev.
O, 09/28/92 I
1
t Reporting Requir:ments 5.9
{
5.9 Reporting Requirements (continued) 5.9.2 Special Reports Special Reports may be required covering inspection, test, and r
maintenance activities. These special reports are determined on an individual basis for each unit and their preparation and submittal are designated in the Technical Specifications.
Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
The following Special Reports shall be submitted:
[
e a.
In the event an ECCS is actuated and injects water into the RCS in MODE 1, 2, or 3, a Special Report shall be prepared t
and submitted within 90 days describing the circumstances of the actuation and the total accumulated actuation cycles to date. The current value of the usage factor for each affected safety injection nozzle shall be provided in this i
Special Report whenever its value exceeds 0.70.
b.
If an individual emergency diesel generator (EDG) experiences four or more valid failures in the last 25 demands, these failures and any nonvalid failures experie:1ced by that EDG in that time period shall be reported within 30 days. Reports on EDG failures shall include the information recommended in Regulatory. Guide 1.9, Revision 3, Regulatory Position C.5, or existing Regulatory Guide 1.108 reporting requirement.
c.
When a Special Report is required by Condition B or G of-LC0 3.3.[17), " Post Accident Monitoring (PAM)
Instrumentation," a report shall be submitted within the 1
following 14 days. The report-shall outline the preplanned alternate method of monitoring, the cause of the l
inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
d.
Any abnormal degradation of the containment structure detected during the tests required by the Pre-stressed Concrete Containment Tendon Surveillance Program shall be reported to the NRC within 30 days. The report shall include a description of the tendon condition, the condition of the concrete (especially at tendon anchorages), the inspection procedures, the tolerances on cracking, and the 1
corrective action taken.
(continued) l BWOG STS 5.0-38 Rev.
O, 09/28/92 P
4 0
t
R: porting Requirements 5.9 1
5.9 Reporting Requirements i
i 5.9.2 Special Reoorts (continued)
Following each inservice inspection of steam generator (SG) e.
tubes, in accordance with the SG Tube Surveillance Program, the number of tubes plugged and tubes sleeved in each SG l
shall be reported to the NRC within 15 days.
t The complete results of the SG tube inservice inspection shall be submitted to the NRC within 12 months following the completion of the inspection. The report shall include:
1.
Number and extent of tubes inspected, 2.
Location and percent of wall-thickness penetration for each indication of an imperfection, and 3.
Identification of tubes plugged and tubes sleeved.
t Results of SG tube inspections that fall into Category C-3 7
shall be reported to the NRC prior to resumption of plant operation. This report shall provide a description of investigations conducted to determine cause of the tube t
degradation and corrective _ measures taken to prevent recurrence.
t i
i i
i r
BWOG STS 5.0-39 Rev.
O, 09/28/92 l
Record Retention 5.10 3
2 5.0 ADMINISTRATIVE CONTROLS 5.10 Record Retention 5
i 5.10.1 The following records shall be retained for at least 3 years:
a.
All Licens'e Event Reports required by 10 CFR 50.73; b.
Records of changes made to the procedures required by Specification 5.7.1.1; and c.
Records of radioactive shipments.
t 5.10.2 The following records shall be retained for at least 5 years a.
Records and logs of unit operation covering time intervals at each power level; b.
Records and logs of principal maintenance activities-inspections, repair, and replacement of principal items of i
equipment related to nuclear safety; c.
Records of surveillance activities, inspections, and calibrations required by the Technical Specifications (TS)
[and the Fire Protection Program];
d.
Records of sealed source and fission detector leak tests and
[
results; and e.
Records of' annual physical inventory of all sealed source material of record.
5.10.3 The followin) records shall be retained for the duration of the unit Operating License:
a.
Records and drawing changes reflecting unit design l
modifications made to systems and equipment described in the FSAR; i
b.
Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories-c.
Records of radiation exposure for all individuals entering-radiation control areas;
.i (continued)
I BWOG STS 5.0-40 Rev.
O, 09/28/92 i
i l
d RhecrdRetentien' 5.10 5.10 Record Retention 5.10.3 (continued)_
d.
Records of gaseous and liquid radioactive material released-to the environs; e.
Records of transient or operational cycles for those unit components identified in [FSAR, Section X];
f.
Records of reactor tests and experiments; g.
Records of training and qualification for members of the unit staff; h.
Records of inservice inspections performed pursuant to the '
l TS; i.
Records of quality assurance activities required by the Operational Quality Assurance (QA) Manual [r.uc listed in Specification 5'10.1 and which are classified as permanent records by applicable regulations, codes, and standards];
j.
Records of reviews performed for changes made to procedures, equipment, or reviews of tests and experiments pursuant to 10 CFR 50.59; k.
Records of the reviews and audits required by Specification 5.5.1 and Specification 5.5.2; 1.
Records of the service' lives of all hydraulic and mechanical snubbers required by [ document where snubber requirements relocated to], including the date at which the service life commences, and associated installation and maintenance records;
[m.
Records of secondary water sampling and water quality;]
n.
Records of analyses required by the Radiological Environmental Monitoring Program that would permit evaluation of the accuracy of the analysis at a later date (these records should include procedures effective at-specified times and QA records showing that these procedures were followed);
i (continued) i BWOG STS 5.0-41 Rev.
O, 09/28/92 i
l
Record R2tentien
-5.1G 5.10 Record Retention 5.10.3 (continued) o.
Records of reviews performed for changes made to the Offsite Dose Calculation Manual and the Process Control Program;
[p.
Records of pre-stressed concrete containment tendon surveillances;] and
[q.
Records of steam generator tube surve111ances].
BWOG STS 5.0-42 Rev.
O, 09/28/92
O 4
[High Radiation Area)
[5.11]
5.0 ADMINISTRATIVE CONTROLS
[5.11 High Radiation Area) 5.11.1 Pursuant to 10 CFR 20, paragraph 20.203(c)(5), in lieu of the requirements of 10 CFR 20.203(c), each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is
> 100 mrem /hr but < 1000 mrem /hr, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP).
Individuals qualified in radiation protection procedures (e.g., [ Health Physics Technicians]) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned-duties in high radiation areas with exposure rates 5 1000 mrem /hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device that continuously indicates the radiation dose rate in the area.
b.
A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.
c.
An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the
[ Radiation Protection Manager] in the RWP.
5.11.2 In addition to the requirements of Specification 5.11.1, areas with radiation levels 21000 mrem /hr shall be provided with locked
-i or continuously guarded doors to prevent unauthorized entry and j
the keys shall be maintained under the administrative control of i
the Shift Foreman on duty or health physics supervision. Doors shall remain locked except during periods of access by personnel (continued)
BWOG STS 5.0-43 Rev.
O, 09/28/92
S L
[High Radiation Area]
r
[5.11]
i l
[5.11 High Radiation Area]
5.11.2 (continued)
[
under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas.
In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.
5.11.3 For individual high radiation areas with radiation levels of
> 1000 mrem /hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shal? be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.
t BWOG STS 5.0-44 Rev.
O, 09/28/92 i
e t'
w Auset31.1993 Revinica 2 INDUSTRY /NRC IMPROVED TEGINICAL SPECIFICATIONS (TTS) NUREG CllANGE PACKAGES
.R Package Chepe rs/
OGS Date Markup Revision Date Comments NRC Reviewer NUREO e
Numher/
- LCO, Affected Provided Indmdual OG Date (If NRC/OGS Updated Comment Affected to NRC/OGS ApplicaMe)
Appenved Numhet LCOs/Bews Attached BWR41 Cl 3.2.4 BWR4 & BWR6 2/19M3 N/A 3/20/93 J. MILLER BWR 41 A Cl 3.3.1.1 BWR4 & BWR6 2/19M3 N/A 3/20M3 J. Miller C2 3.10.8 BWR4 & BWR6 2/19!93 N/A 3/20/93 J. MILLER BWR42 C.I I.i BWR4 & BWR6 2/19/93 N/A 3/20M3 C SCilULTEN C2 1.1 BWR4 & BWR6 2/19/93 N/A 3/20M3 C SCitULTEN C.)
1.1 BWR4 & BWR6 2/19M3 N/A 3/20M3 C. SCllULTEN C4 1.1 ALL OGS 2/19/93 N/A 3/20/93 C. SCliULTEN CS 3.3 ALL OGS 2/19/93 N/A 3/20M3 (J h m =.
C. SOlVLTEN C.6 1.3 BWR4 & BWR6 2/19/93 N/A 3/20/93 C. SCHULTEN C.7 I.3 ALL OGS 2/19/93 N/A 3/20M3 C. SCIlULTEN C8 B.2.1.1.B.2.1.2 ALL OGS 2/19/93 N/A 3/20M3 C SCHULTEN CRe B.2.1.1.B.2.1.2 ALL OGS 2/1993 N/A 3/20M3 C SCllULTEN C9 B.2.1.2 BWR4 & BWR6 2/19/93 N/A 3/20M3 C SCllULTEN C.10 SR 3.0.3 ALL OGS 2/19/93 c.lo st.13/2*'3 3/20/93 c"'se
.m m,- - m m C.SOIULTEN C.Il LCO 3.0.3 ALL OG3 2/19M3 N/A 3/20M3 C SCIIULTEN Cl2 B 3.0 BWR6 2/19/93 N/A 3/20M3 C SCliULTEN BWR43 C.1 3.4.9.3.4.10 BWR4 & BWR6 2/19/93 N/A 3/20M3 J. MILLER C2 3.4.9.3.4.10 BWR4 & BWR6 2/19/93 N/A 3/20/93 J. Miller C3 3.4.10 BWR4 & BWR6 2/19/93 N/A OPEN (J a'e F8m e a=*'* h= a '*c a* a * * *** *
- J. MILLER C4 3.9.8 BWR4 & BWR6 2/19/93 N/A 6/29/93 J. MILLER C.5 3.9.9 BWR4 & BWR6 2/19/93 N/A 3/20/93 J. MILL Ert C.6 3.9.9 BWR4 & BWR6 2/19/93 N/A N/A esse mm w Fsm mw wim J. MILLER WOG41 C.I 1.1 WOG 2/19/93 N/A 3/20/93 R. GIARDINA C2 9 3.0 All OGS 2/19/93 N/A 3/20/93 R. CIARDINA WOG42 m
C.I 3.2.2 WOG 2/19/93 N/A 3/20M3 P.11 EARN C.2 8 3.1.10 WOG 2/19/93 N/A 3/20/93 P.IIEARN
-d C.3 9 3.1.10 WOG 2/t9/93 N/A 3/20/93 P. ItEARN O,,
C4 83.2.1 WOG 2/19M3 N/A 3/20M3 P.IIEARN
.c g
CS B 3.2.3 WOG 2/19/93 N/A 3/20/93 P. If EARN y'
- C6 9 3.l.6,8 3.2.1,B 3.2.2.
WOO. BWOG 2/19/93 N/A 7/28/93 P.IIEARN C.7 83.1.7 WOG 2/19/93 N/A 7/28/93 P.HEARN O
au
.. ~.
_ -. ~. _ _ _...,
- ~...
4 Augunt 31.1993 Revision 2 INDUSTRY /NRC IMPROVED TECilNICAL SPECIFICATIONS (ITS) NUREG Cl{ANGE PACKAGES 2
Pack se Charem/
003 Dere Markup Revimen Date Comments NRC Reviewer ~
NUREG Nuavher/
LCOs Affected Previded Individual OG Date (If NRCIOGS Opdased Comment Affected to NRC/OGS Applicable)
Approved Number LCOsalam Attached WOG42 (continued) 2 C8 83.1.8 WOG 2/19/93 N/A 8/26M3 P.HEARN 1g9 3.2.4.83.2.4 WOG 2/19/93 N/A OPEN P.HEARN CIO B 3.1.6.B 3.t.5 WOG.BWOG 2/19/93 N/A 3/20/93 P.IIEARN Cil B 3.l.1 WOG 2/19/93 N/A 3/20/93 P.HEARN WOG43 Cl 3.1.4 WOG 2/19/93 N/A 3/20/93 R. GIARDINA C2 3 3.t.5 --
WOG 2/19M3 N/A 3/20/93 R. GIARDIN A C.3 B 3.1.7 WOG 2/1983 N/A 3/20M3 R. GI ARDINA C.4 83.1.8 WOG 2/19/93 N/A 3/20/93 R. GI ARDTN A C5 B 3.1.9 WOG 2/19/93 N/A 3/20/93 R. GIARDINA C6 8 3.1.10 WOG 2/19M3 N/A 3/20M3 R. GIARDINA C.7 B 3.2.1 WOG 2/19/93 N/A 3/20'93 R. GIARDINA C8 B 3.t.5 WOG 2/19/93 N/A 3/20/93 R. GIARDINA WOG44 C.I 3.6.6 PWR 005 2/19M3 N/A 3/20/93 R. CI ARDINA WOG45 Cl B 3.9.1 WOG,8WOG 2/19/93 N/A 3/20/93
- 3. MILLER C.2 B 3.9.4 WOG 2/I9/93 N/A 3/20M3
- 3. MILLER C3 B 3.9.4.9 3.9.3 WOG.BWOG 2/19/93 N/A 3/20M3 L MILLER C4 B 3.9.5 WOG 2/19/93 N/A 3/20/93
- 3. MILLER WOG46 C.I 5.6.4 ALLOGS 2/19/93 N/A 3/20/93 R. CIARDINA C2 5.7.1.2 ALL OGS 2/1963 N/A 3/20M3 R. GIARDINA C.3 5.7.2.3 ALL OGS 2/19/93 N/A 3/20M3 R. GIARDINA C4 5.7.2.14 ALL OGS 2/19M3 N/A 3/20/93 R. GI ARDINA C5 5.7.2.15 ALL OGS 2/19/93 N/A 3/20M3 R. GIARDINA C6 5.7.2.17 ALL OGS 2/19M3 N/A 3/20/93 R. GIARDINA C7 5.1.1.1.b ALL OGS 2/19M3 N/A 3/20M3 R. GIARDINA BWOG41 Cl 3.1 ALL OGS 2/19/93 N/A 3/20M3 C SCHULTEN C2 1.1 ALL OG5 2/19/93 N/A 3/20M3 C SCI 1ULTEN
~ C.3 1.1 ALL OGS 2/19/93 N/A 3/20M3 C SCHUL 17.N C4 I.1 PWR 005 -
2/19M3 N/A 3/20/93 C SCllVLTEN C5 1.2 -
ALL OGS 2/19/93 N/A 3/20M3 C SCHULTEN C6 1.3 ALL 005 '
2/19M3 N/A 3/20/93-C. SCHULTEN
/1 ---C7 1.3 ALL OGS 2it9/93 N/A' 3/20/93 C SCHULTEN
~
a W
~
Argust 31,1993, Revime 2 INDUSTRY /NRC IMPROVED TECHNICAL SPECIFICATIONS (ITS) NUREG CHANGE PACKAGES 3_
Package Chapsers/
OGS Date Martup Revision Date Comments NRC Reviewet NUREG Number /
LCOs Affected Provated Individual OG Date (If NRC/OGS Uplatal Comment Afreced to NRC/OGS Applicable)
Approved Number LCOs/Baes Attached EWOG41 (continued)
C.8 l.3 ALL OGS 2/19M3 N/A 3/20/93 C. SCHULTEN C9 1.3 ALL OGS 2/19/91 N/A 3/20M3 C SCIlULTEN C10 LCO 3.0.2 ALL OGS 2/19/93 N/A 3/20!93 C. SCHUL 1EN Cll SR 3.0.4 ALL OGS 2/19/93 N/A 3/20M3 C. SCHULTEN BWOG42 C.1 3.4.14,3.4.6 ALL OGS 2/19/93 N/A 3/20/93
- 3. MILLER C.2 3.4.14.3.4.6 ALL OGS 2/19/93 N/A 3/20M3 L MILLER C3 3.4.16,3.4.7.3.4.8 ALL OGS 2/1983 N/A 3/20/93
- 3. MILLER liWR.04 C.I
- 3. I.1 BWR4&BWR6 3/19/93 N/A 4/22/93 C SOlULTEN C.2 3.1.2 BWR4&BWR6 3'1983 C2 R.17/29/93 4/22/93 c4 6 a
<m a t ne m
C. SCHULTEN C.3
- 3. 3.3 BWR4&BWR6 3/19/93 C.3 R.17/29M3 4/22M3 e3 n,, e m,>.sn e i. nee e m C. SCflULTEN C4 3.1.4 BWR6 3/1953 N/A 4/22/93 C SCIlULTEN C.3 83.1.3 BWR6 3/19/93 N/A 4/22/93 C SCHULTEN C6 NOT USED C.SCHULTEN C.7 3.6.2.1 BWR4&BWR6 3/1953 N/A 4/22/93 C SCHULTEN C8 3.6.4.3 BWR4ABWR6 3/19/93 N/A 4/22M3 C. SCIIULTEN C9 3.8.9 BWR6 3/19/93 N/A 4/22M3 C. SCHULTEN CIO B 3.9.4 BWR4&BWR6 3/19/93 N/A 4/22M3 C SCliULTEN WOG47 C.i 3.3.1 WOG 3/1953 N/A 4/22/93 R. GIARDINA C2 3.3.1 WOG 3/19/93 N/A 4/22M3 R. CIARDINA -
C3 NOT USED R. GIARDINA C4 3.3.1 WOG 3/19M3 N/A 4/2253 R. GIARDINA C.3 3.3.1 WOG 3/1953 N/A 4/22/93 R. GIARDINA C6 3.3.6 WOG 3/19M3 C.6 R.I 5/20/93 N/A C"U8 *'**== =sa N "ee N
R. GIARDINA C7 93.3.1 WOG 3/19M3 N/A 4/22M3 R. GIARDINA C8 B 3.3.1 WOG 3/19/93 N/A 5/20/93 ca e u s.e e u t, e.> s. me,
.+.e.m R. GIARDINA C9 B 3.3.1 WOG 3/19/93 N/A 4/2253 R. GI ARDINA C.10 NOT USED R. GIARDINA C.Il B 3.3.1 WOG 3/19M3 N/A 4/22/93 R. GIARDINA C12 B 3.3.1 WOG 3/19/93 N/A 4/22/93 R. GIARDINA Cl3 83.3.1 WOG 3/19/93 N/A 4/22M3 R. GIARDINA C14 B 3.3.1 WOG 3/19/93 N/A 4/22M3 R. GIARDINA CIS 3.3.1 WOG 3/19/93 C.15 R.2 7/13193 7/28/93 cd8 *===="a=8 m "e **'8 =
R. GIARDINA C 16 -
B 3.3.6 WOG 3/19/93 N/A 4/22/93 R. GIARDINA a
--m m-
.m,
e V
3.
Aeged 31.1993 Revisina 2 INDUSTRY /NRC (MPROVED TECHNICAL SPECITICAllONS (ITS) NUREG CHANGE PACKAGES 4
Pedage Chapters /
OGS Date Martup Revisina Date NRC/OG3 Comments NRC Remmer NUREG Numtw/
LCOs affected P vvided Indivuhant OG Dste (If Agtroved Updated Conwent Affected to NRC/OGS Arpirable)
Number LCon/ Bases Attached WOG4 C1 3.3.3 WOG 3/19/93 N/A N/A c 8 h e*
R. GIARDINA C.2 3.3.7. 3.3.16 WOG.BWOG 3/19/93 N/A 4/22/93 R. GIARDINA C3 3.3.8 WOG 3/19M3 c.3 R.t s/2am 7/28M3 c3% W
-'*="**8'"
N * "-
R. GIARDIN A C.4 93.3.4 WOG 3/19M3 N/A 5/20/93 R. GIARDINA CS B 3.3.5 WOG 3/19/93 N/A 5/20/93 R. GIARDINA C6 B 3.3.7 PWR OG3 3/19M3 N/A 5/20M3 c eggg m, w m m *
- C.2 3.4.8,3.4.19-WOG CEOG 3/1943 OPEN c2 = w mM..
P.HEARN C.3 3.4.10 WOG. CEOG 3/19/93 N/A 4/22M3 P.HEARN C4 3.4.15 PWR OGS 3/19M3 N/A 4/22/93 P.HEARN C5 B 3.4.2 WOG 3/19/93 N/A 4/22/93 P.HEARN C6 B 3.4.4 WOG CEOG 3/19/93 N/A 4/22/93 P.HEARN C7 B 3.4.5 WOG 3/19/93 N/A 4/22/93 P.HEARN 1
C8 8 3.4.10 PWR OG3 3/19M3 N/A 4/22M3 P.HEARN C9 93.4.1I WOG CEOG 3/19/93 N/A 4/22/93 P.HEARN Cto B 3.4.12 WOG, CEOG 3/19M3 N/A 4/22M3 P.HEARN C.Ii B 3.4.12 WOG 3/1953 N/A 4/22/93 P.HEARN WOG.10 C1 B 3.5.1 WOG 3/19/93 N/A 4/22/93 R. GI ARDINA C2 B 3.5.4 WOG 3/19/93 N/A 4/22/93 WOG-l1 R. G!ARDINA C.I B 3.6.2. 4. 6 8 PWROGS 3/19M3 c.: a a 7/2893 7/23/93 c.gge.nyg7thT."*,.T J. MILLER C.2 B 3.6.3 WOG CEOG 3/19M3 N/A 4/22M3
- 3. MILLER C3 B 3.6.4 PWR OG5 3/1919J c.3 a.s 7/28m 7/28/93 cJmm-,. m.a:aisees a a.s m = w w m J. MILLER C4 93.6.6 WOG CEOG 3/19M3 N/A 4/22/93 J. MILLER C5 93.6.8 WOG 3/19/93 N/A 4/22/93
- 3. MILLER C6 B 3.6.8 WOG, BWOG 3/19/93 cA a.t 7/2tm 7/28M3 c4 m, me a.: m. noe m.
J. MILLER WOG-t 2.
C.1 3.7.8 WOG 3/19M3 N/A 4/22/93 R. GtARDIN A C2 3.7.10.3.7.11 PWR OG3 3/19M3 N/A 4/22/93 R. GIARDINA C3 B 3.7.7 WOG 3/19M3 N/A 4/22/93 R. GIARDINA C4 B 3.7.17 WOG 3/19/93 N/A 4/22M3 R. GIARDINA C.5 B 3.7.18 WOG 3/1993 N/A 4/22M3 R. GIARDINA
a Argust 31,1993, Revision 2 INDUSTRY /NRC IMPROVED TECitNICAL SPECIFICATIONS (ITS) NUREG OIANGE PACKAGES 5
Packege Chapters /
OGS Date Markup Revision Date Comments NRC Reviewer NUREO Numtw/
LCOs Affected Premdal Individ'ast OG Date (If NRC/OGS Updated Comand Affectal to NRCIOGS Apriicable)
Arproved Nurnber LCOs/Baws Ausched WOG-13 Cl NOT USED R. GIARDINA C2 3.8. t ALL OGS 3/19M3 N/A 4/22/"
R. GIARDINA C3 3.8. I WOG 3/19M3 N/A 4/22M3 R. CIARDINA C.4 3.8.3 WOG. BWR4 3/19/93 N/A 4/22/93 R. GIARDINA -
J.5 3.8.4 ALL OGS 3/19/93 c.s R.: s/26/93 OPEN CJ"*Ca"'**'****-**="'a=*''*'d"'J R. GIARDINA C6 B 3.8.1 WOG 3/19M3 N/A 4/22/93 V
R. GIARDINA C7 B 3.8.1 WOG 3/19M3 N/A 4/22M3 R. GIARDINA C8 B 3.8.2 ALL OGS 3/19/93 N/A 7/28M3 R. GIARDINA C.9 83.8.3 ALL OGS 3/19/93 N/A 4/22/93 R. GIARDINA CIO B 3.8.3 ALL OGS 3/19/93 N/A 4/22M3 R. GIARDINA Cll B 3.8.3 ALL OGS 3/1933 N/A 4/27/93 R. GIARDINA C12 B 3.8.5 ALL OGS 3/19M3 N/A 4/22/93 R. GIARDINA BWOG43 Cl 3.9.4 BWOG 3/19/93 N/A 4/22/93 C. MOON C2 3.9.5 PWR OGS 3/19M3 N/A 4/22M3 C. MOON C.3 3.9.4 PWR OGS 3/19M3 N#A 4/22M3 C. MOON C4 3.9.2 BWOG 3/19M3 N/A 4/22/93 C. MOON C.5 3.9.5 DWOG, CEOG 3/19M3 N/A 4/22/93 C. MOON C6 3.9 PWR OGS 3/19/93 N/A 4/22/93 C MOON BWR45 c.1 1.1 ALL 005 4/22M3 c.I R I 6'2943 6/29/93 cm mm,*
C SCHULTEN C.2 1.1 BWR4&6.CEOG.BWOG 4/22M3 N/A 5/20/93 C.SGIULTEN C.)
1.1 ALL OGS 4/22/93 N/A 5/20M3 C. SalULTEN C4 1.1 BWR4&BWR6 4/22/93 CM *ad m * *=a'* **'*= N C. SCHULTEN C5 I.!
BWR4&BWR6 4/22M3 N/A 5/20/93 C SCl(ULTEN C.6 1.1 BWR4&BWR6 4/22/93 N/A 5/20/93 C. SCHULTEN C7 LCO 3.0.3 ALL OGS 4/22M3 N/A 5/20/93 C. SCHULTEN
,/
C8 BWR4&BWR6 4/22/93 N/A 5/20M3 y
C SCHULTEN L-C.9 LCO 3.0.5 ALL OGS 4/22M3 f N *** N
- r * *
- C. SCllULTEN
- C.10 B 3.0 ALL OGS 4/22/93 c.to m.s 6/29H OPEN C* * =*==* M h e=*8 *
- m m C. ScitULTEN C.11 B 3.0 BWRd4BWR6 4/22M3 c1 R. e/2993 7/28M3 e a
- d =*
- N N
- ==r====d
)
C SCIIULTEN Cl2 B 3.0 ALL OGS 4/22/93 N/A 5/20/93 C.SCHULTEN
-C 13 B 3.0 ALL OGS 4/22/93 c.13 R I 6t29/93 OPEN u m.e =4e m %,=m4 - % en e.**c C. SCHULTEN Cl4 1.4 ALL 005 442/93 N/A 5/20/93
'/
C. SCIIULTEN CIS B 3.0 ALL OGS 4/22/93 N/A 5/20/93 C SCilULTEN l
- ~
m e
b i
August 31,1993 Revision 2 INDUSTRY /NRC IMPROVED TECHNICAL SPECIFICATIONS (ITS) NUREG OfANGE PACKAGES 6
Pecksgo -
Qispten/ -
OGS Does Marbp Revisica Date Comments NRC Reviewer NUREG.
Number /
LCon' Affected Provided Individual 00 Date (If '
NRC,0GS Up4 meed -
Comment Anected to NRC/OGS ApphesMe)
Approved Number LCOs/ Banes Attactwd BWR46 Cl 1.1 BWR4aBWR6 4/22/93 N/A 5/20/93 C SolVLTEN -
Cl l.1 BWR4 4/2253 N/A 5/20/93 C. SCITULTEN C.3 1.4 ALL OGS 4/22M3 CJ R.l eMM 6/29M3
'J"*c====**=******"
C. SclIULTEN C.4 3.6 BWR4&BWR6 4/22M3 N/A '
5/20/93 C. SOfUL17.N C.5 3.6 BWR4&BWR6.WOG 4/22/93 N/A 5/20/93 C. SO{ULTEN i
C.6 NOT USED C**"
C. SCitULTEN -
C7 5.9.2 ALL OGS 4/22/93 N/A 5/20M3 C. SCHULTEN C8 5.10 ALL 005 4/22/93 N/A 5/20M3 C. SCHULTEN C.9 3.3 ALL 005 4/22/93 C 9 R.2 tem OPEN e e w = m =. mm-.e w = =m.'
C. SclULTEN BWR #"**"***"
M.I 3.8.1 ALL OGS 4/22/93 C.t R 18mM OPEN BWR48
~
C s %.= e ue ss a n===== e4==i.,wnef"'6=**
C. SCHULTEN
~
i Cl 3.8.7 ALL OGS.
4/22M3 C.I R.I tem OPEN.
e ' e' "*e -a=== * *=== * *
^ * = = =
E. TOMUNSON C.2 3.8.7 ALL OGS.
4/22/93 C.I R.I 7mm OPEN ODY[m7,"m77, "
E. TOMUNSON C3 3.8.7 ALL OGS 4/22M3 C 1 R.I ?mm OPEN
-*==**===**="r E. TOMLINSON I
C.4 B 3.8.9 BWR4&6.WOG.CEOG 4/22/93.
C.I R.I 7mm OPEN E. TOMUNSON WOG.14 Cl 3.8.4 ALL OGS 4/22M3 N/A 5/20/93 E. TOMUNSON QWOG-04 C.I 3.4.16 ALL OGS 4/22/93 -
N/A 5/20/93 E. TOMUNSON BWOG-05 Cl 3.8.1.3.8.4 ALL OGS 4/22M3 N/A 5/20/93 E. TOMUNSON NRC-01 Cl 4.0 ALL OGS 4/22M3 N/A 5/20/93 N/A C2 B 3.7 ALL OGS 4/22/93 N/A 5/20M3 N/A C3 3.3.8 CEOG 4/22/93 N/A E3"*e*"*===**='====**
N/A C4 B 3.3.3 -
CEOG 4/22/93 N/A c e n.a.=r e==e w o
.==c w m pfA C5 3.3.5 WOG 4/22M3 N/A t.8 ===*== ~ *aa' *
- N/A C.6 3.3.2. I BWR4 4/22M3 N/A -
c s **==,====e *= =====e m N/A C7 3.3.2.1.
BWR4 4/22/93 N/A 5/20/93 -
N/A C8 3.3.5.1.
BWR4 4/22/93 N/A C 8 **="r * ** "*c===8 h N/A C.9 3.3.8.1 '
BWR4 -
4/22/93 OPEN
- "**=='=*="**=='=r=***'*"=*=*
N/A OPEN}
N/A C.10 3.3.8.1 '
BWR6 4/22/93.
Cll 3.3.8 '
BWOG 4/22/93 OPEN!/-
N/A
' Cl2 3.3.8.1 CEOG.A '
4/22/93 OPEN (
N/A Cl3 3.3.8.1 CEOG-D 4/22/93 OPEM_.) :
N/A r
-. _ - _,.. _. _. _. ~.....
, -,... -.. _ _ _..,... -. _.. -. ~.. _ -. --... - _.. _. _...,- __.
e August 31.1993. Revisimi 2 INDUSTRY /NRC IMPROVED TECHNICAL SPECIFICATIONS (ITS) NUREG CHANGE PACRAGES 7
Pack *se Cbspiers/
005 Date Martup Revisme Date Comments NRC Reviewee NUREG Number /
LCOs Affected Pnmded Indivnfmal Date (if NRC Updatal Commmt AfTeeml k
OG Applicatde)
/OG5 Number NRC/OG5 LCOvBaws Approved Attached NRC-02
/
C1 VAR]OUS All OG5 5/20/93 N/A 7/28/93 V c'**==v==d****=*=***=**h"'ced****==d*'
N/A C.2 5.7.2.15 ALL 0G5 5/20M3 N/A 5/20M3 c2** =
N/A C.3 83.3.1 BWOG 5/20/93 N/A 5/20M3 N/A C4 B 3.7.5 BWOG 3/2033 N/A 5/20M3 N/A C5 3.3.4 CEOG 5/20M3 N/A 5/20/93 N/A C6 B 3.6.3 CEOG 5/20/93 N/A 5/20/93 e s = =n.
N/A C7 B 3.3.3.B 3.6.6 CEOG 5/20M3 N/A 5/20M3 N/A C8 83.7.7 CEOG 5/20/93 N/A
$/20/93 N/A C9 5.5.1.1 CEOG 5/20/93 N/A 5/20/93 N/A C10 5.7.2.15. 5.9 CEOG 5/20/93 N/A 5/20/93 e h = **
N/A CII B 2.1.2 WOG 5/2033 N/A 5/20/93
( " h **
N/A C.12 B 3.6.3 WOG 5/20/93 N/A 5/20M3 c '8 6 *"-
N/A Cl3 5.7.2.16 WOG 5/20/93 N/A 5/20/93 N/A Cl4 3,1.4 BWR4 5/20M3 N/A 5/20M3 N/A Cl3 B 3.3. B 3.6 BWR4 5/20/93 N/A 5/20/93 N/A C16 B 3.6.l.3 BWR4 5/20/93 N/A 5/20/93 N/A C.17 83.1.8 BWR6 5/20M3 N/A 5/20/93 N/A Cl8 8 3.3. B 3.6 BWR6 5/20M3 N/A 5/20!93 N/A C19 B 3.6.1.3 BWR6 5/20/93 N/A 5/20/93 N/A C20 B 3.8.4 BWR6 5/20/93 N/A 5/20M3 N/A C21 VARIOUS ALL OG5 5/20M3 N/A 5/20M3 N!A C.22 5.7 BWR4 5/20M3 N/A 5/20/93 carme.,
w.m w mm m
m m
gfA C.23 3.8 I PWR OG5
$/20/93 c.23 m.17c'93 8/26/93 C" *d
- P="d * * *8 " * *= *'* "
N/A CI 4.0 All. 005 5/20/93 N/A OPEN c 8 "*e =*=**
B%%.10 C.SCHULTEN CI LCO 3,0,4 ALL OG5 5/20M3 OPEN c'* =aa+ /
C. SCHULTEN Cl 5.7.2.13 PWR OG5 5/20/93 OPEN---
C'*****"*
- ""'*"d"b*""'*'
R. TJADER WOG.16
" ' ' * * * ~ * "- /
Cl 3.2.3 WOG 5/20/93 N/A 6/29/93 R. TJ ADER C2 3.2.3 WOG 5/2053 N/A 6/29/93 CEOG41 R. T3ADER C1 3.8.6 Al.L OG5 5/20/93 N/A 6/29/93 E. TOMUNSON C2
- 3. 8.6 ALL OG5 5/20M3 c.2 m. e/2943 7/28M3 C J **""* r="** **d *** =* h"" *==*== 8 J "'" "ne s
- E. TOMUN50N C3 83.8.6 ALL OG5 5/20/93 N/A 6/29/93 E. TOMUNSON C4 93.8.6 ALL OG5 5/20/93 N/A 6/29/93 E. TOMUNSON C.5 B 3.8.6 ALL OG5 5/20/93 c.5 a.t tr2933 7/28/93 CJ**""r****="***d**=*""***""**"d'"-
E. TOMLINSON
y-A tP
~
Acgust 3 t.1993. Revisme 2 INDUSTRY /NRC IMPROVED TECilNICAL SPECIFICATIONS (ITS) NUREG CHANGE PACKAGES S
Package Chapters /
003 Date Markup Revision Date Comments NRC Revic*ee NUREG Number /
LCOs Affected Provided Individual OG Date (If NRC/OG5 Updatal Comment Affected to NRC/OG5 Applicable)
Approved Number LCOs/Baws Attached NRC43 Cl 3.1 BWOG 5/20M3 N/A 5/20M3 N/A C2 1.1 BWOG 5/20/93 N/A 5/20M3 N/A C3 1.1 BWOG 5/20/93 N/A 5/20M3 N/A C.4 1.1 BWOG 5/20M3 N/A 5/20/93 N/A WC5 3.0.7 WOG,BWOG 5/20/93 OPEN CJ **ar W * *..
N/A C.6 3.1.1 BWOG 5/20/93 N/A 5/20/93 N/A C7
- 3. t.3 BWOG 5/20/93 N/A 5/20M3 N/A C8 3.3.3 ALL OG5 5/20M3 N/A
$/2053 c ' a== =6'-* **c====d -i-aa m N/A C9 3.5.2,ETC WOG,CEOG,8WOG 5/20M3 OPEN c ' haar * *'==* w a='**a = w*
- w [
N/A
- C10 3.5.5 BWOG 5/20M3 -
8/26/93 v'
c a m* =* **'w a'a m ire a ====> -== = -
N/A NRC44 CI 3.7 PWROG5 5/20M3 N/A 5/20r93 c.' * **'"E N/A NRC45 Cl B 3.3.6 WOG 5/20M3 N/A 5/20M3 N/A C2 B 3.3.3 WOG 5/20M3 N/A 5/20/93 N/A-C3 93.3.5 WOG 5/20/93 N/A 5 M3 N/A CEOG Cl 3.3.11 CEOG 5/25/93 N/A 6/29M3 C SCliULTEN C.2 3.4.17 CEOG 5/25/93 NIA 6/29/93 C SCIIULTEN C3 3.9.2 PWR 0G5 5/25/93 N/A 6/29/93 C. ScilULTEN WOG-11 C1 3.1.5 WOG 5/25M3 N/A 6/29/93 P.HEARN C2 3.1.8 WOG 5/2553 N/A 6/29/93 P. IfEARN C3 3.l.10 WOG 5/25/93 N/A 6/29/93 P.IIEARN C4 3.2.1 WOG 5/25/93 N/A 6/29/93 P.HEARN C5 3.2.3 WOG 5/25/93 N/A 6/29/93 P.IIEARN WOG.t s Cl 3.2.4 WOG
$/25/93 OPEN -
c"'c e 'ran..on === e ' * *
- WOG.19
~ ~~
~'
C SCHULTEN Ci 3.6. 3.7 PWR OGS
$/2533 c.t n.1 s/2M3 7/28/93 ew C SCilUllTN
[gm % ha'== W
- m= h a i eien =c WOG-20 Cl B 3.4.12 WOG. CEOG 5/25/93 c.: n.s st2M3 t/26/93 F8 * ***= "*===* **=d 'a= *" h u m ac W R. GIARDINA '
h C2 B J.4.12 WOG. CEOG 5/25/93 8/26/93 R. GIARDINA C3 8 3.4.12 WOG. CEOG 5/25/93 8/26/93 R. GIARDINA
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Aeget 31,1993, Revision 2 (NDUSTRY/NRC IMPROVED TECHNICAL SPECIFICATIONS (ITS) NUREG CHANGE PACKAGES 9
Package Chapters /
OGS Date Markup Revisico Date Comments NRC Revwwer NUREG Number /
LCOs Affectal Pmvuled Indivutual 00 Date (If NRC/OGS Updated Comment Affected to NRC/tX;S Applicable)
Appeswed Numbee LCodews Attactwd WOG-21 C1 2.2 WOG 6/29/93 N/A 7/28M3 P.HEARN C2 B 2.1.1 PWR OGS 6/29/93 N/A 7/28/93 P.HEARN C.3 B 3.1.1 WOG 6/29'93 N/A 7/28M3 P.HEARN C4 B 3.1.2 WOG 6/29/93 N/A 7/28M3 P. IIEARN C.5 B 3.1.5 WOG. BWOG 6/29/93 N/A 7/28/93 P. IIEARN C6 B 3.l.3 PWR OG3 6/29M3 N/A 7/28/93 P.HEARN C.7 93.1.6 WOO 6/2953 N/A 7/28!93 P.HEARN C.8 93.1.7 WOO 6/29M3 N/A 7/28/93 P.HEARN C9 B 3.1.7 WOG,CEOG 6/29193 N/A 7/28/93 P.HEARN.
CIO B 3.1.8 WOG BWOG 6/29/93 N/A 7/28/93 P.HEARN Cll B3.1.9.83.1.10 WOG,CEOG 6/2953 N/A 7/28/93 P.HEARN C.12 B.3.1.1. B 3.1.2 WOG 6/2953 N/A 7/28/93 P.HEARN WOG-22 Cl NCTP USED P.HEARN C.2 B 3.2.1 WOG 6/29/93 N/A 7/28/93 P.HEARN C.)
B 3.2.1 WOG 6/29/93 N/A 7/28/93 P.HEARN C4 83.2.2 WOG 6/29/93 N/A 7/28/93 P. IIEARN C.5 B 3.2.2 WOG 6/2953 N/A 7/2&l93 P.HEARN C6 B 3.4.14 ALL OGS 6/29/93 N/A 7/28/93 P. IIEARN C.7 B 3.4.2 WOG, CEOG 6/29/93 N/A 7/28/93 P. IIEARN C8 B 3.4.5 WOG 6/29/93 N/A 7/28/93 P.HEARN C9 B 3.4.7 PWR OGS 6/29/93 N/A 7/28/93 P.HEARN CIO B 3.4.7 WOG 6/29/93 N/A 7/28/93.
P.HEARN C.1i B 3.4.7 PWR OGS 6/29/93 N/A 7/28/93 P.HEARN Cl2 B 3.4.8 WOG 6/29/93 N/A 7/28M3 P.HEARN Cl3 8 3.4.14 PWR OGS 6/29/93 N/A 7/28/93 P.HEARN WOG-23 Cl B 3.5.5 WOG 6/29/93 N/A OPEN eN * %
C. MOON C2 NOT USED 6/29/93 N/A C. MOON C3 3.6.5 WOG 6/29/93 N/A 7/28/93 C. MOON C4 83.6.2 WOG 6/29/93 N/A OPEN ed"*e ~ **==
C. MOON C5 NOT USED 6/29/93 C. MOON C6 93.6.6 WOG, BWOG 6/29/93 N/A OPEN c 8 "*e *==* 6*== =
C. MOON C.7 NOT USED 6/29/93 C. MOON ~
CS B 3.6.10 WOG 6/29/93 N/A OPEN e8"'cw % n C. MOON C9 9 3.6.10 WOG 6/29/93 N/A OPEN c ' "me===* % =
C MOON C.10 B 3.6.14 WOG 6/2953 N/A OPEN c.'s **e w t'a== ='*="s-C. MOON Cli B 3.6.19 WOG 6/29/93 N/A OPEN emsec===a % %
C MOON l
+
e Arget 31,1993 Reviseen 2 INDUSTRY /NRC IMPROVED TEC).NICAL $2ECIFICATIONS (ITS) NUREG CllANGE PACKAGES 10 Package Clarters/
OGS Deee Markup Reviam Date Comments NRC Reviewer NUREG Numher/
LCOs Affweed Provided indsvidual OG Dete(H NRC/OGS Updatal Comment Affected to NRC/OGS Applicable)
Approved Number LCOvBaws Attached WOO.24 WOG.BWOG, C.1 3.7.1i BWR4 & BWR 6 6/29M3 N/A 7/28M3 J. MILLER C.2 B 3.7.1 WOd.BWOG 6/2943 N/A 7/28M3 J. MILLER C3 83.7.2 WOG 6/29/93 N/A 7/28M3 J. MILLER C.4 B 3.7.3 WOG.BWOG 6/29/93 N/A 7/28/93 J. MlU ER CS B 3.7.10 WOG.BWOG 6/29/93 N/A 7/28M3 J. MILLER C.6 B 3.7.13 WOO 6/2953 N/A 7/28/93 J. M111ER C.7 NOT USED 6/29/93 J. MILLER C8 NOT USED 6/29/93 J. MILLER C9 4.0 ALL OGS 6/29M3 N/A OPEN ^
c'"'c"'a'* N h*=' *
- h "
J. MILLER N C.10 NOT USED
~ ~
J. MILLER 6/29/93
~
BWR-ll Cl 2.1 BWR4, BWR6 6/29/93 N/A 7/28M3 C SCHULTEN -
C2 2.1 BWR4, BWR6 6/29M3 N/A 7/28/93 C. SCHULTEN C.3 B 2.1.1 BWR4, BWR6 6/29/93 N/A 7/28/93 C. SCilVLTT.N C.4 B 2.1.1 BWR4, BWR6 6/29M3 N/A 7/28M3 C. SCIIULTEN C.3 B 2.1.1 BWR4, BWR6 6/29/93 N/A 7/28/93 C. SCHULTEN C6 B 2.1.l BWR4, BWR6 6/29/93 N/A 7/28M3 C SCIIULTEN C.7 B 2.1.1 BWR4, BWR' 6/29/93 N/A 7/25/93 C. SCIIULTEN C8 B 2.1.1 BWR4, BWR6 6/29/93 N/A 7/28M3 C. ScilULTEN C.9 B 2.1.2 BWR4, BWR6 6/29/93 N/A 7/28/92 C. SCIIULTEN C.10 B 2.1.2 BWR4, BWR6 6/29/93 OPEN c","==='==****===**********=ad""e*====
C. ScilULTEN C.II B 2.1.2 BWR4, BWR6 6/29/93 OPEN e "p " **== m. 'mo *=* * *=== = Y-C. SCHULTEN Cl2 B 2.2.4 BWR4, BWR6 6/29/93 OPEN cd'y "
- N **= *** N w "
C SCHUL 1EN NRC-06 W.I 4.0 FWR OGS 6/29M3 OPEN cd h*==, *==* m*** ",*c e=**
- h. wo*e men
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Acgue 31,1993.Revena 2 INDUSTRY /NRC IMPROVED TEGINICAL SPECIFICATIONS (ITS) NUREO GIANGE PACKAGE 5 11 Packe8e Chapters /
OG3 Date Martup Revision Date Comments NRC Reviewer NUREG Number /
LCOn Affectal Provided Individual OG Date (W NRC/OG5 Uptisted Comment A! Tectal to NRC/OG5 Agyiicable)
Approved Number LCOs/ Bases Attached WOG.23 Cl 3.3. B 3.3 WOG 6/29/93 N/A 7/28/93 C. SCilULTEN C2 3.3. B 3.3 WOG 6/29/93 c.2 a.2 7ns33 OPEN e2****=*'*==***"*'2" C. SCliULTEN CJR'74'*3 7/28/93 esnoe wasm
- % mee'"*
C.Scl1ULTEN C.3 3.3, B 3.3 WOG 6/29/93 C.4 3.3, B 3.3 WOG 6/29/93 c.4a.:7nsn3 OPEN e*h*='*a*-8*=='t*****e''===8**=**
C.SOIULTEN C.3 3.3 B 3.3 WOG 6/29/93 N/A 7/28/93 C. SCilVLTEN C6 3.3, B 3.3 WOG 6/29/93 N/A 7/28M3 C. SCHULTEN C.7 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C. SCIIULEN C8 3.3. B 3.3 WOG 6/29/93 C8R1741M3 OPEN c ' * *"*'d **'*"* e.a
- C. ScitULEN C9 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C SCHULTEN C.10 3.3, B 3.3 WOG 6/29/93 c.no n.2 7nsM OPEN e ha'* **'* *='= :
1*'2" C. SC11ULTEN
[
CII 3.3 B 3.3 NOT USED C SCHULTEN h C.12 3.3, B 3.3 WOG 6/29/93 c.12 sti 7at33 7/28/93 can me e.=, m ma.i. w w = n 8 = -
C SGtULTEN Cl3 3.3. B 3.1 WOG 6/29/93 N/A 7/28/93 C SGIULTEN Cl4 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C. ScitULTEN
. Cl3 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C. SCHULEN CI6 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C SCilULTEN C.17 3.3, B 3.3 WOG 6/29/93 N/A 7/29/93 C 501ULTEN C18 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C SOlULTEN C.19 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C. SCHULTEN -
C.20 3.3. B 3.3 WOG 6/29/93 -
N/A 7/28/93 C 50{ULTEN C.21 3.3, B 3.3 WOG 6/29/93 c.21 R.I 7t2sM3 OPEN c2'**=****=**'*'8'**=d*2*
C SCHULTEN C.22 3.3, B 3.3 WOG 6/2983 N/A 7/28/93 C.SatULTEN C23 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C. SC11UL17,N C24 3.3, B 3.3 WOG 6/29/93 c.24 m.: ?nsas 7/28/93 c'""ea==****='"a*****==v'p==8*=*****""
C. SCHULTEN C.25 3.3, B 3.3 PWROG3 6/29/93 c.23 R.i tr2s83 OPEN e 8 h*== ="
- h' W **8 '2 ***
C. ScitULTEN C.26 3.3, B 3.3 WOG 6/29/93 N/A 7/28/93 C SCllULTEN C27 3.3, B 3.3 WOG 6/29/93 c.27 a.17a*H OPEN car see wsm me m e 8 ***
C. SCIIULTEN WOG 26 C1 NOT USED P.HEARN C.2 WOG 6/29/93 N/A 7/28/93 P.IIEARN C3 WOG 6/29/93 N/A 7/28/93 P.HEARN C.4 ALL OG5 6/29/93 N!A 7/28/93 P.IIEARN C3 PWROG5 6/29/93 N/A 7/28/93 P.IIEARN
e August 31,1993, Revisica 2 INDUSTRY /NRC IMPROVED TECllNICAL SPECIFICATIONS (ITS) NUREO CllANGE PACKAGES 12 Packsge Chapeen/
OGS Deee Markup Revision Dam Comments NRC Reviewer NUREO Number /
LCOs Affected Provi&d Individual 00 Date (If NRC/OGS U deted P
Comment Afrected to NRC/OGS Applicable)
Agyroved Number LCom/Baws Attacimi BWR.13 Cl 3.1 BWR4 & BWR6 7/29 S 3 OPEN C. MOON C2 3.1 BWR4 & BWR6 7/29/93 -
OPEN C. MOON C.3 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C4 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C.5 3.1 BWR4 & BWR6 7/2953 OPEN C MOON C6 3.1 BWR4 & BWR6 7/29M3 OPEN C. MOON C7 3.1 BWR4 & BWR6 7/2953 OPEN C. MOON C8 3.1 BWR4 & BWR6 7/29/93 OPEN C MOON C.9 3.1 BWR4 & BWR6 7/29/93 OPEN C MOON CIO 3.1 BWR4 & BWR6 7/29M3 OPEN C MOON C.Il 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C.12 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C.13 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C.14 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON Cl3 3.1 BWR4 & BWR6 7/2953 OPEN C. MOON C.16 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C17 3.1 BWR4 & BWR6 7/29M3 OPEN C. MOON C.18 3.1 BWR4 & BWR6 7/29M3 OPEN-C. MOON CI9 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C20 3.1 BWR4 & BWR6 7/29/93 OPEN C. MOON C21 3.1 BWR4 & BWR6 7/29/93 OPEN C MOON W OG-27
-Cl SR 3.7.5.3 & 4 PWR OGS 7/29M3 8/26M3 Y
- 0. GI ARDINA NRC47
- C.I 3.6.8 ALL OGS 7/29/93 OPEN f
" N * -* = a r-aati a" N/A NRC48 i
C.1 5.7.2 ALLOGS 7/2953 OPEN M c2****"'- * * = ' * * ' = * = =
N/A
^~
' ' ~ '
BWOG46 Cl 3.8.1 PWR OGS 8/26/93 OPEN R. GIARDINA B%2-12 C1 3.4.7 & 3.4.8 BWR4 & BWR6 8/26M3 OPEN R. VADER WOG Cl B 3.3.1 PWR OGS 8/26/93 OPEN R. CIARDINA NRC49 Cl B 3.7.1 CEOG 8/26/93 OPEN N/A NRC.10 Cl 5.5.1 & 3.5.2 ALL OGS 8/26/93 OPEN N/A
~ - -
e
~
August 31,1993 Revision 2 INDUSTRY /NRC IMPROVED TECIINICAL SPECIFICATIONS (ITS) NUREG CHANGE PACKAGES 13 Package Chapeen/
OGS Date Marby Revisica Date Commmts NRC Reviewer NUREO Nambert LCOs Affected Provided Inchvidual 00 Dets (If NRC/OG5 Updatat Comment AtTeeted to NRC/OGS Applicable)
Approved Number LCOa/ Bases Attached NCC-Il C.I 3.4.10 & 3.4.12 BWOG 8/26/93 OPEN N/A
{'
l-1
'o OPEN ITEMS OG/NRC_ Packages for review ~ August,1993 Reviewer Date In BWR 08 RI PH 9/2 (inverter)
WOG 28 RG 9/3 (accumulator)
WOG 13 R1 RG 9/3 (battery term) l BWR 07 Cl R1 CS 9/3 (bases consist)
'BWOG 06 RG 8/30
P 1
l i
a
y Y,,...
t ENCLOSURE 6 ACTION ITEMS l
12 PRPB Offgas Monitor position (3.4.12 &
GENERIC: Awaiting resolution of PAMS).
related DPV.
20 OTSB pursue generic concern of tripped-GENERIC: 0TSB initiate evaluation i
state vulnerabilities.
-of tripped-state risks.
i 30 OTSB pursue backfitting Delay LOOP /LOCA GENERIC:
OTSB initiate evaluation
]
surveillance for all plants.
to determine whether to backfit:
delayed LOOP tests.
Information Notice 93-17-identified concern, but i
EELB believes further generic action may be warranted.
42 OG develop revised Bases to explain H IMPLEMENTATION: OG provided l
2 control capabilities to backup suggested lists of backups, but'NRC recombiners, mixing, or CAD to preclude concluded must be case-by-case loss-of-function.
review depending on the plant-specific licensing basis. OTSB reviewer note submitted to OG in
<<NRC-07>> on 7/28/93 60 OG develop admin controls for Tendon COMPLETE: Tendon Program.
l Surveillance and SG Tube Surveillance Administrative Control programs.
COMPLETE:
OG proposed program l
submitted for NRC Engineering review. OG proposal rejected per Russell letter of 6/23/93. OG to appeal on 8/12/93.
i 67 OTSB trace removal of surveillance COMPLETE:
Restored SR for BWR-4 requirement for drywell-wetwell vacuum vacuum breaker surveillance.
breakers within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after steam discharge.
GENERIC:
0TSB evaluate need for i
BWR-6 vacuum breaker surveillance.
Awaiting response from SCSB.
75 Evaluate redundancy of turbine-drive AF IMPLEMENTATION: OTSB concluded must pump to motor-driven AF pump for PWRs.
be case-by-case review depending on i
the plant-specific licensing basis.
OTSB reviewer note submitted to OG i
with traveller (<<NRC-02-23>>).
OG' response provided~in Rev. I on 7/28/93.
108 Clarify Required Actions for loss of.
IMPLEMENTATION: OG proposal made in i
inverter power.in LCO 3.8.7.
May (<<BWR-08)>).
OTSB proposed alternate in June. OG rejected OTSB proposal.
OG provided <<BWR-08,-
_j R1>> on 7/29/93.
l l
l
v'
~
ACTION ITEMS 1
Action Description Status' 109 Deletion of requirement to have a COMPLETE:
Reliable RCS temperature shutdown cooling subsystem in monitoring is an important safety operation, since this requirement is function. OG should address in only provided to ensura accurate comments on shutdown requirements.
reactor coolant temperature monitoring.
Reconsider BWROG 2/13/92 comments.
BWR4: 3.4.8, 3.4.9, 3.9.7, and 3.9.8 Awaiting SRXB response.
SRXB' BWR6: 3.4.9, 3.4.10, 3.9.7, and 3.9.8 rejected in 7/13/93 memo.
110 Deletion of shutdown cooling COMPLETE: There should be a requirements when heat losses to demonstrable need for such an ambient are sufficient to maintain exception, established on a case-by-reactor coolant temperature (similar to case basis. 0G should address in Perry and Fermi-2 technical comments on shutdown requirements.
specifications).
Reconsider BWROG 2/13/92 comments.
BWR4: 3.4.9, 3.9.7, 3.9.8, and 3.9.9 Awaiting SRXB response.
SRXB BWR6: 3.4.10, 3.9.7, 3.9.8 and 3.9.9 rejected in 7/13/93 memo.
111 Revision of the positive reactivity COMPLETE:
NRC rejected OG proposal insertion Required Actions to allow per memo from Reactor Systems Branch normal makeup and cooldown activities.
dated 4/28/93.
0G evaluating possible appeal based on Byron /
W: 3.3.1, 3.3.9, 3.8.2, 3.8.5, 3.8.8, Braidwood amendment.
3.8.10, and 3.9.3 112 One hour instead of 15 minutes for GENERIC:
It is not apparent that securing an RHR pump in Mode 5 with the the subcooling provision would RCS Loops not filled, as long as RCS provide adequate protection over the temperature is maintained 2 10 range of conditions of interest. 0G subcooled.
should address in comments on shutdown requirements.
113 Required Action B of LCO 3.4.6, GENERIC:
During Mode 4 when the RCS
" Initiate actions to restore an DHR temperature is above 200 F, if only Loop OR place the Unit in Mode 5."
one RHR train is operable and two required RCS loops are inoperable, PWR: 3.4.6 the unit should be brought to Mode 5 within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. OG should address in comments on shutdown requirements.
1 i
STS Status Dated:
8/5/93
t-ACTION ITEMS f_ -
Action Description Status 114 LC0 3.9.4, LC0 note prior to proof-and-GENERIC: The basis-for allowing DHR review allowed DHR to be removed from to be removed from operation for up operation for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> per 24-hour to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in a 24-hour period is period.
not clear. The staff believes that allowing DHR to be-removed from B&W: 3.9.4 operation for up to one hour in an 8-hour period is appropriate, with due consideration for decay heat removal.and boron stratification concerns. 0G should address in comments on shutdown requirements.
116 Establish consistent PAM requirements IMPLEMENTATION: OTSB proposed two' for single-channel parameters.
options to OG following review of uBWR-06>> package. OG provided Rev. I to uBWR-06>> 6/30/93. NRC accepted with change. OG provided Rev. 2 to uBWR-06>> 7/28/93.
119 Restructure Chapter 5.0.
IMPLEMENTATION: OG informed of NRC (0GC) position on requirements to restructure. 0G completed matrix to prioritize sections for removal.
OTSB to develop plan to restructure Chapter 5.0.
122 Develop admin control for LCO on SI/HPI IMPLEMENTATION:
OG position pumps in modes 5 and 6 to permit one submitted in May (uWOG-20>>).
train of injection available for makeup OTSB/SRXB evaluating.
uWOG-20>>
capability when LTOP analyses do not accepted with changes and provided account for more than charging pumps.
to OG 7/28/93. Meeting to be scheduled with SRXB to discuss separation of LPS issues.
124 Develop clarification for LC0 3.0.4:
IMPLEMENTATION: OG proposal not applicable for plant shutdown.
submitted in May (uBWR-10>>). OTSB to forward to SRXB for-review. OTSB needs-to address staff concern.
125 ISI/IST for snubbers IMPLEMENTATION: Model TS provided to OG.
OTSB provided new model TS to OG in uNRC-08>> on 7/29/93.
126 PTLR/LTOP IMPLEMENTATION: Chapter 5.0 description of PTLR given to OG.
Memo-requesting EMCB comments issued. 0G provided response to j
NRC-proposed change to 5.0.
OTSB requested markup of 5.0 reflecting OG position.
]
STS_ Status Dated: 8/5/93
'1
. :.
- a ACTION ITEMS Action Description Status 127 OPDRVs OG position requested 6/29/93 on WNP-2 experience.
BWROG provided results of poll of BWR utilities.
PWROG to submit traveller to delete OPDRVs from STS.
OTSB will pursue BWR issue with technical staff.
P b
t t
i
'STS Status Dated:
8/5/93 i
Q N October 25, 1993 Future meetings are scheduled as follows: September 22-23, 1993, Irvine, CA and October 20-21, 1993, New Orleans, LA. There will be no meeting in November 1993.
Ori inal Signed by:
9 C. I. Grimes Christopher I. Grimes, Chief Technical Specifications Branch Division of Operating Reactor Support, NRR
Enclosures:
As stated cc w/o enclosures:
cc w/ enclosures:
T. Murley W. Hall, NUMARC W. Russell L. Bush, OG J. Partlow DISTRIBUTION: w/ enclosures DISTRIBUTION w/all enclosures except Enclosure 4
_N entral Files DORS R/F JACalvo CERossi C
PDR CIGrimes GClainas BABoger OTSB R/F OTSB Staff JAZwolinski FJCongel MSchwartz, OGC MJVirgilio DMCrutchfield SAVarga JTWiggins DPAllison, CRGR JWRoe ACThadani JHConran, CRGR CMarco 1
DOCUMENT NAME: A:\\0TSBRE1 OTSB: DOR :NRR SC:0
' DORS:NRR BC:0TSB: DORS:NRR C
RHLo CIGrimes ATChu
/f/2ff9
[o /t 93 g) /g6/9
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