ML20149M767
| ML20149M767 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/22/1988 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20149M746 | List: |
| References | |
| NUDOCS 8802290059 | |
| Download: ML20149M767 (13) | |
Text
.
ADMINTSTRATIVE CONTROLS 6.2.3 STATION SAFETY REVIEW GROUP FUNCTION 6.2.3.1 The Station Safety Review Group (SSRG) shall function to examine plant operating characteristics, NRC issuances, industry advisories, Licensee Event Reports and other sources which may indicate areas for improving plant safety.
COMPOSITION 6.2.3.2 The SSRG shall be composed of at least five dedicated, full-time engineers located onsite.
RESPONSIBILITIES 6.2.3.3 The SSRG shall be responsible for maintaining surveillance of plant activities to provide independent verification
- that these activities are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.4 The SSRG shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving plant safety to the Director, Nuclear Safety Review Board.
RECORDS 6.2.3.5 Records of activities performed by the SSRG shall be prepared, maintained, and forwarded each calendar month to the Director, Nuclear Safety Review Board.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Superv'sor.
6.3 UNIT STAFF OUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifica-tions of ANSI N18.1-1971 for comparable positions and the supplemental require-ments specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees, except for the Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
T [c 6.4 TRAINING 6.4.1 A retraining and replacement training program for' the unit staff shall be maintained under the direction of the Station Manager,dand shall meet or exceed the requirements and re:Ormendati;ns ;f :: tion 5.5 Of,'95: N10.1-1071 end Arponais A of 10 CFR Part 55.and the supple. ental cequice.mcnts specified in Sections ^ :nd C Of Enci;;ure i af ttm Mei ch ZG,1300 NRC ic tici ali vu
'icen :::, :nid : hall include fa.ailiai;&aLivn wiwh.ciuvant indu Lij vgaiaLivuoi experi:nc; identified by tr.e RG.
- Not responsible for sign-off function.
McGUIRE - UNITS 1 and 2 6-7 0802290059 880222 DR ADDCK 05000369 p
No Changes Info. dnU l
ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.1.1 Each procedure and program required by Specification 6.8 and other procedures which affect nuclear safety, and changes thereto, shall be prepared by a qualified individual / organization.
Each such procedure, and changes thereto, shall be reviewed by an individual / group other than the individual /
group which prepared the procedure, or changes thereto, but who may be from the same organization as the individual / group which prepared the procedure, or changes thereto.
- 6. 5.1. 2 Proposed changes to the Appendix A Technical Specifications shall be prepared by a qualified individual / organization.
The preparation of each proposed Technical Specifications change shall be reviewed by an individual /
group other than the individual / group which prepared the proposM change, but who may be from the same organization as the individual / group whicn prepared the proposed change.
Proposed changes to the Technical Specifications shall be approved by the Station Manager.
6.5.1.3 Proposed modifications to unit nuclear safety-related structures, systems and components shall be designed by a qualified individual / organization. g Each such modification shall be reviewed by an individual / group other than the individual / group which designed the modification, but who may be from the same organization as the individual / group which designed the modification.
Proposed modifications to nuclear safety-related structures, systems, and components shall be approved prior to implementation by the Station Manager; or by the Operating Superintendent, the Technical Services Superintendent, the Superintendent of Integrated Scheduling, or the Maintenance Superintendent, l
as previously designated by the Station Manager.
6.5.1.4 Individuals responsible for reviews performed in accordance with 6.5.1.1, 6.5.1.2, and 6.5.1.3 shall be members of the station Specifications supervisory staff, previously designated by the Station Manager to perform such reviews.
Each such review shall include a determination of whether or not additional, cross-disciplinary, review is necessary.
If deemed necessary, such review shall be performed by the appropriate designated station review personnel.
6.5.1.5 Proposed tests and experiments which affect station nuclear safety and are not addressed in the FSAR or Technical Specifications shall be reviewed by the Station Manager; or by the Operating Superintenderit, the l
Technical Services Superintendent the Maintenance Superintendent, or the Superintendent of Integrated Scheduling as previously designated by the Station Manager.
Amendment No.52(Unit 1)
McGUIRE - UNITS 1 and 2 6-8 Amendment No.33(Unit 2)
ADMINISTRATIVE CONTROLS ACTIVITIES (Continued) 6.5.1.6 ALL REPORTABLE EVENTS and all violations of Technical Specifications shall be investigated and a report prepared which evaluates the occurrence and which provides recommendations to prevent recurrence.
Such reports shall tm approved by the Station Manager and transmitted to the Vice President, Nuclea.-
Production, and to the Cir; t:r 0 t % Nuclear Safety Review Board.
}
- 6. 5.1. 7 The Station Manager shall assure the performance of special reviews and investigations, and the preparation and submittal of reports thereon, as requested by the Vice President, Nuclear Production.
- 6. 5.1. 8 The station security program, and implementing procedures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved by the Station Manager or Superintendent of Station Services and transmitted to the Vice President, Nuclear Production, and to the i zt:r Of M : Nuclear Safety Review Board.
6.5.1.9 The station emergency plan, and implementing proceaures, shall be reviewed at least once per 12 months.
Recommended changes shall be approved g
by the Station Manager and transmitted to the Vice President, Nuclear Produc-l tion, and to the Circ tcr f the Nuclear Safety Review Board.
6.5.1.10 The Station Manager shall assure the performance of a review by a qualified individual / organization of every unplanned onsite release of radio-active material to the environs including the preparation and forwarding of reports covering evaluation, recommendations, and disposition of the corrective ACTION to prevent recurrence to the Vice President, Nuclear Production and to the Nuclear Safety Review Board.
6.5.1.11 The Station Manager shall assure the performance of a raview by a qualified individual / organization of changes to the PROCESS CONTROL PROGRAM, OFFSITE 00SE CALCULATION MANUAL, and Radwaste Treatment Systems.
6.5.1.12 Reports documenting each of the activities performed under Specifi-cations 6.5.1.1 through 6.5.1.11 shall be maintained.
Copies shall be provided to the Vice President, Nuclear Production, and the Nuclear Safety Review Scard.
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)
FUNCTION The NSRB shall function to provide independent review and audit of 6.5.2.1 designated activities in the areas of:
a.
Nuclear power plant operations, b.
Nuclear engineering, c.
Chemistry and radiochemistry, McGUIRE - UNITS 1 and 2 6-9 Amendment No.
Unit 1)
Amendment No.
(Unit 2)
No Chancjes ADMINISTRATIVE CONTROLS FUNCTION (Continued) d.
Metallurgy, Instrumentation and control, e.
f.
Radiological safety, Mechanical and electrical engineering, and g.
h.
Administrative control and quality assurance practices.
ORGANIZATION The Director, members and alternate members of the NSRB shall be 6.5.2.2 appointed in writing by the Vice President, Nuclear Production, and shall have an academic degree in an engineering or physical science field; and in addition, shall have a minimum of 5 years technical experience, of which a minimum of 3 years shall be in one or more areas given in Specifica-tion 6.5.2.1, No more than two alternates shall participate as voting members in NSRB activities at any one time.
6.5.2.3 The NSRB shall be composed of at least five members, including the Director.
Members of the NSRB may be from the Nuclear Production Department, A
from other departments within the Company, or from external to the Company.
maximum of one member of the NSRB may be from the McGuire Nuclear Station staff.
6.5.2.4 Consultants shall be utilized as determined by the NSRB Oirector to provide expert advice to the NSRB.
6.5.2.5 Staff assistance may be provided to the NSRB in order to promote the proper, timely, and expeditious performance of its functions.
6.5.2.6 The NSRB shall meet at least once per calendar quarter during the initial year of unit operation following fuel loading and at least once per 6 months thereafter.
l 6.5.2.7 The quorum ~ of the NSRB necessary for the performance of the NSRB review and audit functions of these Technical Specifications shall consist of the Director, or his designated alternate, and at least four other NSRB members including alternates.
No more than a minority of the quorum shall have line responsibility for operation of McGuire Nuclear Station.
i 6-10 McGUIRE - UNITS 1 and 2
ADMINISTRATIVE CONTROLS REVIEW 6.5.2.8 The NSRB shall = % be. respons.6le, er t-A4. eevie w 8 :
a.
The safety evaluations for:
(1) changes to procedures, equipment, or systems, and (2) tests or experiments completed under the provision of Section 50.59, 10 CFR to verify that such actions did not constitute an unreviewed safety question; b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; c.
Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR; Proposed changes in Technical Specifications or this Operating o.
License; Violations of Codes, regulations, orders, Technical Specifications, e.
license requirements, or of internal procedures or instructions having nuclear safety significance; f.
Significant operating abnormalities or deviations from normal and expected performance of unit equipment that affect nuclear safety;
~
g.
All REPORTABLE EVENTS;
$o h.
All recognized indications of an unanticioated deficiency in some aspect of design or operation of structures, systems or components that could affect nuclear safety; i.
Quality Assurance Department audits relating to station operations and actions taken in response to these audits; and J.
Reports of activities performed under the provisions of Specifi-cations 6.5.1.1 through 6.5.1.11.
AUDITS 6.5.2.9 Audits of unit activities shall be performed under the cognizance of the NSRB.
These audits shall encompass:
The conformance of unit operation to provisions contained within the l
a.
Technical Specifications and applicable license conditions at least once per 12 months; The performance, training, and qualifications of the entire unit b.
I staff at least once per 12 months; 1
Amendment No.
(Unit 1) l McGUIRE - UNITS 1 and 2 6-11 Amendment No.
(Unit 2)
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
Procedures for the recording and management of data, 4)
Procedures defining corrective actions for all off-control 5) point chemistry conditions, and (a) the authority responsible for the A procedure identifying:
6) interpretation of the data, and (b) the sequence and timing of administrative events required to initiate corrective action, Backup Method for Determining Subcoolino Marain d.
A program which will ensure the capability to accurately monitor the Reactor Coolant System subcooling margin.
This program shall include the following:
1)
Training of personnel, and 2)
Procedures for monitoring, Post-accident Samoling e.
A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines, and particulates in plant gaseous effluents, and containment atmosphere samples under accident conditions.
The program shall include the following:
1)
Training of personnel, 2)
Procedures for sampling and analysis, and Provisions for maintenance of sampling and analysis equipment.
3) 6.9 REPORTING REQUIREMENTS a
[
ROUTINE REPORTS In addition to the applicable reporting requirements of Title 10, Code i
of Federal Ragulations, the following reports shall be submitted to the 2;;': :1-6.9.1 I
I Adr -J :t :'
' the uqC Regionc! Of'ic:
wid le crR Phee sc.4.
i STARTUP REPORT A summary report of plant STARTUP and power escalation testing shall 6.9.1.1 (1) receipt of an Operating License, (2) amendment to be submitted following:
the License involving a planned increase in power level, (3) installation of fuel that has a different design or nas been manufactured by'a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
Amendment No.
(Unit 1)
Amendment No.
(Unit 2) 6-16 McGUIRE - UNITS 1 and 2
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REP 0_RT*
6.9.1.6 Routine Radiological Environmental Coerating Reports covering tne operation of the unit during the previous calendar year shall be sucmittec prior to May 1 of each year.
The initial report shall be suomitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of tne results of the radiological environmental surveillance activities for the report perioc, :nciuuing a comoarison with crecoerational studies, with coerational co'trols is 1:0-co"a*.a.
and witn previous environmental surveillance reports, and an assessment of :ne The reports snall observed impacts of the plant operation on the environment.
also include the results of land use censuses required by Specification 3.12.2.
-onolyse s The Annual Radiological Environmental Operating Reoorts shall include 4ae summodyd ond tob:Imed results o' :r:1y:i: of all radiological environmental samoley"and >( all environmental radiation measurements taken during the period pursuant to tne
^
locations specified in the Table and Figures in the 00CM
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In the event that some individual results are not availacie fernsar. "cw e;;e.
for inclusion with the report, the report shall be submitted noting and exclaining tne reasons for the missing results.
The missing data shall be submitted as soon as possible in a supplementary report.
.The reports shall also include the following:
a summary description of the Radiological Environmental Monitoring Program; at least two legible maps **
covering all samoling locations keyed to a table giving distances and directions from the centerline of one recctor; the results of licensee participation in
- ne Interlacoratory Comparison Program, required oy Soecification 3.12.3; oiscussion of all deviations from the samoling senedule of Tacle 3.12-and discussion of all analyses in wnicn tne LLO required by Taole 4.12-1 w.u not acnievaole.
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT ***
Routine Radioactive Effluent Release Reports covering the coeration 6.9.1.7 of the unit during the previous 6 months of operation shall de submitted The period of the within 60 days after January 1 and July 1 of each year.
first report shall begin with the date of initial criticality.
A single submittal may be made for a multiole unit station.
i
-n One map shall cover stations near the site boundary; a second snall include l
==
the more distant stations, The suomittal A single submittal may be made for a multiple unit station.
=
i should combine those sections that are common to all units at the station; l
however, for units with separate Radwaste Systems, the submittal snail specify the releas'es of radioactive material from each unit.
l McGUIRE - UNITS 1 and 2 6-18 l
ADMINISTRATIVE CONTROLS SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)
The Radioactive Effluent Release Reports shall include the following information.for each typ,of solid wacte shipped offsite during the report period:
h Total container volume, in cubic meters, a.
Total Curie quantity (determined by measurement or estimate),
b.
Principal radionuclides (determined by measurement or estimate),
c.
Type of waste (e.g., dewatered spent resin, compacted dry waste, 4
d.
evaporator bottoms),
Number of shipments, and e.
6 Solidification agent or absorbent (e.g., cement, or other approved 5
f.
agents (media)).
The Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Radioactive Effluent Release Reports shall include any changes made during the reporting period to the PROCESS CONTROL PROGRAM (PCP) and to the OFFS 00SE CALCULATION MANUAL (ODCM), as well as a listing of new locations for dose calculations and/or environmental monitoring identified oy the land use census pursuant to Specification 3.12.2.
MONTHLY OPERATING REPORTS Routine reports of operating statistics and shutdown experience, ll including documentation of all challenges to the PORVs or safety valves, sha
- 6. 9.1. 8
"; nag:-
be submitted on a monthly basis to the 0irc:t;r Office of t ;;;r :%r kaohington. C. C i th ; 0;;;y -
m i
m;nt, U.S. "uc1e?" Dag-1ctory Cc 4 !
ian the 15th of each month following the t; the " C o gicaa' 0"4ce, no later t e
calendar month covered by the report. w r<R C.s ace,,. don eg. u,A.,
t0CrA Sc.4 i
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Amendment No.
(Unit 1) 6-20 McGUIRE - UNITS 1 and 2 Amendment No (Unit 2)
ADMINISTRATIVE CONTROLS 6.9.1.9 PEAXING FACTOR LIMIT REPORT ND The W(z) Functions for RAOC and Base load operation and the value for APL (as required) shall be established for each reload core and implemented prior y(
to use.
t The methodology used to generate the W(z) functions for RAOC and Base Load
(
Operation and the value for APL shall be those previously reviewed and ap-h NO proved by the NRC*.
If chan es to these methods are deemed necessary they will
(
be evaluated in accordance w th 10 CFR 50.59 and submitted to the NRC for re-view and approval prior to their use if the change is determined t) involve an
)
unreviewed safety question or if such a change would require amendment of pre-(
viously submitted documentation.
)(
A report containing the W(z) functions for ROAC and Base Load operation and
)
ND the value for APL (as required) shall be provided to the NRC document con-(
trol desk with copies to the regional administrator and the resident inspector within 30 days of their implementation.
h NU Any information needed to support W(z), W(z)BL and APL will be by request from the NRC and need not be included in this report.
ne c m a e coro' ncL wA o
6.9.2 Special reports shall be submitted to the 4qi: 01 Ad "ist*="" c' *e M C 9 qi: d Of' Re within the time period specified for each report.
/0 C CR 50 61 b
4 7 Surveillance Tech-g
- WCAP-10216 "Relaxation of Constant Axial Offset Control-Fq 7
nical Specification".
f McGUIRE - UNITS 1 and 2 6-21 Amendment No.
(Unit 1)
Amendment No.
(Unit 2)
u y
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ATTACHMENT 2 i
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Justification for Technical Specification Changes The proposed changes to the McGuire Nuclear Station Technical Specifications are administrative and are associated with:
1)
Nuclear. Safety Review Board (NSRB) 2)
Training (in consideration of revised 10CFR 55) 3)
Reporting Requirements (in consideration of revised 10CFR 50.4) and format Section 6.4, Training The proposed changes to Section 6.4 are intended to eliminate redundancy between the Technical Specifications and the Regulations.
The revision to Title 10 of the Code of Federal Regulations, Part 55, issued March 25, 1987 and effective May 26, 1987, rendered this section of the Technical Specifi-cations redundant to the regulations.
Eliminating redundancy between the Technical Specifications and the Regulations is one area that has been iden-tified as an area for improvement in the Technical Specifications.
Additional changes to 6.4.1 reflect the new position of Manager, Station Training Services, and the deletion of reference to the SSRG.
The Manager, Station Training Services is a new position, and this person has responsibil-ity for the unit staff training program conducted at the site. The removal of reference to the SSRG is due to the fact that the group is not directly involved in the Operating Experience Program.
Identification of relevant operating experience information for use in training programs is explicitly a part of the Operating Experience Program and appropriate responsibilities have been clearly assigned to a separate group.
As these propcsed changes to the Technical Specifications simply remove redundancy and clarify re sponsibilities, these are purely administrative changes and have no adverse safety consequences.
Section 6.5, Review and Audit The proposed changes in Section 6.5 are all editorial changes.
The proposed changes to Specifications 6.5.1.6, 6.5.1.8, and 6.5.1.9 reflect the change in title of the person in charge of the NSRB and makes the wording consistent with that contained in Specifications 6. 5.1.10 and 6.5.1.12.
The proposed changes do not affect the actual review process.
The proposed change to 6.5.2.8 to change "The NSRB shall review:" to "The NSRB shall be responsible for the review of:" is a clarification of responsibili-ties and is consistent with the wording in the Catawba Nuclear Station Tech-nical Specifications.
The Nuclear Safety Review Board is charged to provide independent review and audit of designated plant activities in the areas listed in the referenced sections. The board carries out its responsibilities with the support of the Nuclear Safety Assurance staff.
Under the Board's direction, the staff reviews documentation of station activities and forwards to the Board copies of documents requiring review. They also provide input to
~
' the Board in the form of summaries and trends of incidents and key results from the reviews of station activities performed by other bodies (e.g. NRC, INPO).
In all cases the board retains responsibility for the final assessment of the conduct of station activities.
The proposed change to the technical specifications would more accurately reflect the review work done directly by the Board as well as the reviews performed for the Board by others.
These changes are editorial changes and do not involve any operational con-cerns nor do they affect the adequacy of the review process.
Section 6.9, Reporting Requirements The proposed changes in Section 6.9 concern the submission of reports and the format of those reports.
Changes in 10CFR Part 50.4 have changed the location to which reports are submitted.
Previously, the Technical Specifications directed reports to the NRC regional of fice (Sections 6.9.1 and 6.9.2) or to the NRC Of fice of Resource Management (Section 6.9.1.8); the new requirement specifies that all communications be directed to the NRC Document Control Desk in Washington.
The proposed changes to 6.9.1, 6.9.1.8, and 6.9.2 bring the Specifications in line with the regulation, as the regulation supersedes the l
Specification in accordance with 10CFR 50.4(f), thus this e nange is purely administrative.
The second change in this Section involves the format of the Annual Radio-logical Environmental Operating Report as specified in 6.9,1.6.
Presently, the Tech. Specs. state that "the Annual Radiological Environmental Operating Reports shall include the results of analysis of all radiological environmen-tal samples and of all environmental radiation measurements taken during the period.
. as well as summarized and tabulated results of these analyses and measurements The change being requested is that the "results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period" be deleted from the Anw2al Radiological Environmental Operating Reports and that only the summarized and tabulated results be included.
Including the individual results of analyses and measurements adds substentially to the size of the report without adding any significant information that is not already included in either the text of the report or the summary of results.
The individual results will remain on file at Duke and will be available for review and examination by NRC inspect-ors, should they desire to review individual results.
An additional change in this paragraph is requested to editorially change the requirements on report format.
The present requirement specifies the format as that of the table in the Radiological Assessment Branch Technical Position, Revision 1 November 1979.
The proposed change simply requires the report to be "in an NRC accepted format". The change thus allows additional flexibility on both NRC and Duke to change, but maintains acceptability to both.
This I
change is thus administrative in nature.
-e
- Analysis of Significant Hazards Considerations Pursuant to 10CFR 50.91, this analysis provides assurance that the proposed changes to the McGuire Nuclear Station Technical Specifications do not involve any significant hazards considerations as defined by 10CFR 50.92.
(1) The proposed chsnges would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes are all administrative in nature and do not impact station operation.
The changes do not change or degrade in any way training or technical review; there is a change in requirements for the Annual Radiological Environmental Operating Report, but the same data will be gathered and available.
None of the proposed changes impact station operation.
(2) The proposed changes would not create the possibility of a new or dif-ferent kind of accident from any accident previously evaluated.
The proposed changes, as previously discussed, do not impact station oper-ation; as the changes are purely administrative, no hardware changes are involved.
Thus, no possible accident scenarios are affected or created by these changes.
(3) The proposed changes would not involve a significant reduc. tion in a margin of safety.
The changes would have no operational impact on any system thus no safety margins are affected.
Based upon the preceding analyses, Duke Power concludes that the proposed amendments do not involve any significant hazards considerations.
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