ML19317G650
| ML19317G650 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 12/12/1974 |
| From: | Davis E, Kaplan D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8003250705 | |
| Download: ML19317G650 (29) | |
Text
.
AEC DISTRICUT CN FOR PART 50 DOCKET :.1 ATERI AL (TE.1?OR ARY FO RT.;)
12875 CONTROL NO:
FILE:
F RO.1: SMJD DATE OF DOC DATE REC'D LTR TV!X RPT OTHER S:cramento, Calif.
95813 X
E K. Davis 12-12-Th 12-29-7h TO:
SENT LOCAL PDR Mr. A. iambusso 1 signed CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXX 1
50-312 XXn ENCLOSURES: Rancho Seco Unit 1 Tech Specs...
DESCR PTION:
Ltr notarized 12-12-74 pursuant to 1G CFR 50.59 request for revisen to Tech-Specs.... submitted as AMUP #30.....trans th o followit t:
(hO cys enc 1 rec'd)
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o-SbAUD SACRAMENTO MUNICIPAL UTILITY DISTRICT C 1708 59th Street, Box 15830. Sacramento, Cahfornia 95813;(916)452 3211 December 12, 1974 Wx
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N Mr. Angelo Giambusso
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Deputy Director for Reactor Projects p
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Directorate of Licensing U.S. Atomic Energy Commission p
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Re: AEC Docket No. 50-312, Proposed Amendment No. 30 Rancho Seco Nuclear Generating Station, Unit No. 1
Dear Mr. Giambusso:
In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby proposes to amend its Operating License DPR-54 for Rancho Seco Nuclear Generating Station, Unit No. 1, by submitting forty (40) copies of Proposed Amendment No. 30.
The purpose of Amendment 30 is to revise the Technical Specification and comply with the Standard Technical Specifications for Section 6,
" Administrative Controls":
1.
Section 1.8 has been revised to comply vith Regulatory Guide 1.16.
2.
Section 4.14 has been revised to agree with the standard terminology used in the Technical Specifications.
3.
Section 6.0 has been completely rewritten to comply with AEC Standard Format.
4.
Paragraph 3.5.2.7 has words "or his uesignated representative" added.
5.
Table 3.5.1-1 has a requirement for Pressurizer Level Channels added.
Mr. Bart Buckley of your office and Mr. Ron Colombo of SMUD agreed that any exceptions to the Regulatory Guide 1.16, Rev. 2, would be stated with this correspondence.
The following exceptions are proposed:
1)
C.l.b (2) shall read:
"For each outage or forced reduction in power of over 20%."
177,.s 77
- w
s Mr. Angelo Giambusso December 12, 1974 2)
C.1.b (2)(f) shall read:
"A report of any single release of radioactivity or unusual radiation exposures specifically associated with outages which account for greater than 10%
of the annual permitted."
3)
C.l.b (3) shall read:
"A tabulation (supplementing the requirements of Section 20.407 of 10 CFR Part 20) of the number of. personnel receiving exposures greater than 100 mr.."
4)'
C.1.b '(4)(a) and (b) and (c) and (d) are to be deleted.
5)
C.2.a shall read:
"The types of events listed below should be reported as. expeditiously as possible but within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, by telephone and confirmed by telegraph, mailgram, or facsimile transmission, the first work day following the event, to the Director of the appropriate.
Information provided on the transcription sheet shall be supplemented, as needed.
6)
C.2.a (1)-shall read:
"Failu're of the reactor protection system to trip, as required, by the time a monitored parameter reaches the value specified as the limiting safety system se: ting in the technical specifications.
Note:
Instrument drift discovered as a result of testing need not be reported under this item."
7)
C.2.a (4) Delete.
8)
C.2.a (5) shall read:
"(4) Reactivity Anomalies involving disagreement of $1.00 between predicted and actual values."
9)
C.2.a (9) shall read:
"(8) Discovery of errors in the transient or accident analyses or in the methods used for such analyses
' as describ'ed in the' safety analysis report.or in the bases for the Technical Specifications that have or could have permitted
~
reactor operation in a manner less conservative than assumed in the analyses."
10)
C.2.b shall read:
" Thirty Day Written Reports.
The Abnormal
- Occurrences discussed below have lesser'immediate importance Such events should be the subject of written reports (transcription. sheets' - see Appendix A to this guide) to the -
Director of the appropriate Regulatory Operations Regional Office within'30 days of the event."
'll)- 1C.2.c shall read:
"c.
Events of Public Interest
. but Las soon as possible."
~
Mr. Angelo Giambusso December 12, 1974 12)
C.2.c (1) shall read:
"(1)
An event that causes substantial property damage."
13)
C.2.c (4) shall read:
"(4)
Discovery of a significant radiological event offsite.
14)
C.2.c (6) shall read:
"(6)
Unusual low-level releases of radio-active material from the site boundary not reported under Item 2.a (4) above."
Respectfully submitted, SACRAMENTO MUNICIPAL UTILITY DISTRICT
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By
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J]b General Manager
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l EFID S. KAPLAN
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General Counsel of Sacramento Mun' ipal Utility District Subscribed and sworn to before me this 12th day of December, 1974.
BER. NOT h
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g gi BETTY MATTIIR,' Notary Publ'ic in and J
i for the County of Sacramento, State I.
of California 4-70 CD i My Commission Expires January 12, 1976 C
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y RANCHO SECO UNIT 1 IlI 7Y TECHNICAL SPECIFICATIONS Definitions D.
All automatic containment isolationvaEvesareoperableor closed in the safety features position.
E..
The containment leakage satisfies Specification 4.4.1, and no known changes have occurred.
1.8 ABNORMAL OCCURRENCE Any of the following:
(1)
Failure of the reactor-protection system to trip, as required, by the time a monitored parameter reaches the value specified as the limiting' safety system setting in the technical specifications.
(2)
Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less j
conservative'than the least conservative aspect of the limiting condition for operation established in the technical specifications.
l (3)
Abnormal degradation of one of the several boundaries designed to contain radioactive material resulting from the fission process.
}-
(4)
Reactivity Anomalies involving disagreement of $1.00 between pre-dicted and actual values.
(5)'
Fa110ra or malfunctinn of one or more components which prevents or could. prevent, by itself, the fulfillment of the functional requirements of systems required to function to cope with acci-dents _ analyzed in the SAR.
30
'-(6)
~ Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfillment of the functional requirements of systems required to function to cope with accidents analyzed in the SAR.
'(7)
Conditions arising from natural or manmade events that, as a direct result of the' event,. require plant shutdown, operation of safety systems, or other protective measures required by_ technical speci-
.I fications.
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(8)
LDiscovery of errors in the transient or accident analyses or in the methods used'for.such analyses as. described in the safety-analysis report or in the bases for' the technical specifications
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that have or could_have permitted. reactor operation in a manner less conservative lthan_ assumed in the analyses.
6 1-5 Amendment 30' a
ABNORMAL OCCURRENCE-(Continued)
(9)
Performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the safety analysis report or technical specifications (including bases) or discovery during plant life of conditions not specifically considered in 3
the safety analysis report or technical specifications that re-
-quire remedial action or corrective measures to prevent the existence or development of an unsafe condition.
1.9 TIME PERIODS i
1.9.1 Shif t - A time period covering 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, three shif ts equally dividing a 24-hour time period.
1.9.2 Daily - A time period within a 24-hour span from 0000 to 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> from Monday.through Sunday.
1.9.3 Weekly - A time period from Monday through Sunday spaced to occur 52 times a year.
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1-Sa Amendment 30 4
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4.14 SAFETY SYSTEMS HYDRAULIC SNUBBERS Applicability Applies to all hydraulic snbbbers installed on safety related systems.
Objective To verify that the hydraulic snubbers will perform their design function.
Specification 1.
Those hydraulic snubbers accessible during plant operation shall be inspected for proper reservoir oil level and evidence of leakage monthly. Those hydraulic snubbers not accessible during plant operation l3 shall be inspected for proper reservoir level and evidence of leakage quarterly.
Any units showing evidence of oil leakage shall be dis-l3 assembled and cause of leakage determined.
If the cause is determined to be seal degradation, all units exposed to a similar or harsher atmosphere shall be disassembled and seals and fluid replaced in accordance with the manufacturer's instructions.
2.
After the fifth year of operation, at least one unit containing ethelene propylene seals and one unit containing polyurethane seals, which are exposed to the most adverse environment (radiation and temperatures),
shall be disassembled and seal-material physical properties evaluated.
If physical properties noted indicate seals are approaching end of useful life, as recommended by snubber manufacturer, all seals in units in a similar atmosphete shall be replaced not later than the next refueling interval.
In addition, if seal replacement is necessary, per above requirements, sample units from areas having less harsh environment shall be disassembled and need for seal replacement determined.
3.
If current test programs or operating experience proves that the continua-tion of this inspection program is not required, this section of the Technical Specifications (4.14) will be deleted.
Justification for this action will be submitted to the AEC in a special report.
Basis The useful life of the seals and fluids being used is not now known.
This surveillance program will monitor seal condition and verify ability of snubbers to perfo m intended design function.
4-47
. Amendment 30
L 6.0-ADMINISTRATIVE CO3TROLS
' 6.1 RESPONSIBILITY 6.1.1 The Plant Superintendent' shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITL 6.2.1 The'offsite organization for facility management and technical support shall be as shown on figure 6.2-1.
FACILITY STAFF 3@
6.2.2 The Facility organization shall be as shown on Figure 6.2-2 and:
a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown.in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
c.
At least two licensed Operators shall be present in the control room during reactor start-up, scheduled reactor shutdown and durinh recovery from reactor trips until system transients have s tabilized, d.
An individual qualified in radiation protection procedures shall be on site when fuel in in the reactor.
e.
ALL CORE ALTERATI0MS after the initial fuel loading shall be-directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator limited to Fuel llandling who has no other concurrent responsibilities during this operation.
6-1 Amendment 30
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e BOARD OF DIRECTORS l
SECRETARY TRCASURER gy ACCOUf4 TANT MANAGEMENT INDEPLf4 DENT CONSU.T ANTS SAF57Y REVIEW PEtilODIC SAFETY AUDif GENE RAL MAN AGER s
OP RANCHO SECO OPER ATIONS CuMMaffEE l
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l PUBLIC RELATIONS '
PE RSONNE L LEGAL.
STAFF ANDINFORMAllON DEPARTMENT ASSISTANT,
ASSISTANT ASSISTANT ASSISTANT GENE RAL%1AN AG E R GENERAL MANAGE R GENER AL MAN AGER GENER AL MANAGE R CONTROLLER TREASURER OPE R ATIONS CHIEF ENGINEER 30 TRISMIM GENERA N ACCOUNTING PURCHASING OPERATIONS ENGINEERING TRANSMISSION /
DATA DISTRIBUTION MARKETING DISTRIBUTION
' PROCES$1NG RANNING ENGINEERING OISTRIBUTION NUCLEAR GENERAL FINANCE CONSTRUCTION /
SERVICES '
OPE RATIONS MAINTENANCE INTERNAL -
CUSTOME R HYOP.O INSURANCE
. AUOSTOR SE RVICES OPE RATIONS ten. RULES.
SYSTEMS AND QUALITY PI'OCEDURES REGULA IONS
'l FIGURE.6.2-1 SMUD ORGANIZATION Qr
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. SMUD FSAR - 600 e.7 72 SACRAMENTO MUNICIPAL UTILITY DISTRICT
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mendment 30 7"
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PLANT SUPERINTENDENT
- TECHNICAL AOMINISTRATIVE ASSISTANT
- STAFF ASST. SUPT.
ASST. SUPT.
MAINTEfJANCE NUCLE AR PLANT TECHNICAL SUPE RVISOR OPER ATIONS (SL)
- SUPPOR T SHIFT MAINTENANCE SUPERVISORS (SL)
PERSONNEL SR. CONTROL ROOM OPER ATORS (L)
FOWER PLANT CHEMICAL.R AOIA TION INSTRUMENT CONTROL ENGINEERS
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OPERATORS (L)
CHEMISTRY.nAO!ATION INSTRUMENT CONTROL PE RSONNEL PERSONNEL AUXILIARY
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OPERATORS SL. SENIOR AEC LICENSE L.
AEC LICENSE EQUIPMENT e.
ROUTINE REPORTING REOUIREMENTS
-ATTENDANTS ON PERSUNNEL CHANGES FIGURE 6.2-2 PLANT ORG ANIZ ATION CH ART RANCHO SECO UNIT 1 -
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS y ' b G
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. CHANGE SMUD FSAR - 228
- ES3' SACRAMENTO MUNICIPAL UTILITY DISTRICT
. m24 72 -
Amendment 30
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE 6.2-1 SHIFT CREW PERSONNEL AND LICENSE REQUIREMENTS ***
REACTOR MODE RANCHO SECO JOB TITLE COLD OTHER THAN SHUTDOWN COLD SHUTDOWN Shift Supervisor 1 - SL 1 - SL Sr. Control Room Operator or Control Room Operator 1-L 2 - L*
Auxiliary Operator or Equipment Attendant 1
1 Equipment Attendant or Power Plant Helper 1
Minimum Total Personnel 3
5**
l1
- 0ne licensed operator when the reactor is shutdown greater than 1%
AK/K.
- In the event that any member of a minimum shift crew is absent or incapacitated due to illness or injury, a qualified replacement shall be designated to report onsite within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
SL - AEC Senior Licensed Operator L - AEC Licensed Operator
- Until such a time as the startup tests and warranty run are completed,'
and sufficient " hot" operator license examinations have successfully completed to provide the shift staffing as indicated on figure 6.2-1, each operating shif t shall censist of at least five persons, includ-ing at least one licensed senior reactor operator, one licensed reactor operator, and one or more senior staff members from either the Plant Staff, qualified members of the Generation Engineering Staff, or NSSS vendor's staff or consultants, who, by virtue of
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their training and experience can provide competent technical support for the startup and power ascension program.
This staff member will not-be required when the reactor is shutdown.by more than 1% AK/K nor when,the full compliment of three licensed operators is available.
6-3 Amendment 30
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ADMINISTRATIVE CONTROLS 6.3 FACILITY STAFF OUALIFICATIONS 6.3.1 Each member of the operating staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions.
6.4 TRAINING 6.4.1
'A retraining and replacement training program for the operating staff shall be maintained under the direction of the Training Supervisor and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEU CO)MITTEE (PRC)
FUNCTION 6.5.1.1 The Plant Review Committee shall function to advise the Plant Superintendent on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The Plant Review Committee shall be composed of the:
Chairman:
Technical Assistant Member:
Operations Supervisor Member:'
Technical Supervisor Member:
Maintenance Supervisor Member:
Radiation and Chemistry Supervisor Other members as the Plant' Superintendent may appoint from time to time.
6-5 Amendment 30
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' ADMINISTRATIVE CONTROLS ALTERNATES l6.5.1.3 Alternate members shall be appointed in writing by the Plant Super-intendent' to serve on a temporary basis; however, no more than two alternates shall participate in PRC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The PRC shall meet at least once per calendar month and as convened by the PRC Chairman.
., UORUM Q
6.5.1.5 A Quorum of the PRC shall consist of the Chairman and two members including alternates.
RESPONSIBILITIES 6.5.1.6 The Plant Review Committee shall be responsible for:
.a.
Review of 1) all procedures required by Specification 6.8 and changes thereto, 2) any other proposil procedures or changes thereto as determined by the Plant Superintendent to affect
' nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
~
- c. _ Review of all proposed changes to the Technical Specifications.
s
-d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety, e.
Investigation of all violations of the Technical Specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Plant Superintendent and to the Chairman of the Management Safety Review Committee.
f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Management Safety
. Review Committee.
6-6 Amendment 30'
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ADMINISTRATIVE CONTROLS-
' RESPONSIBILITIES (Continued) 4 h.
Review of the Plant Security Plan and implementing procedures and sL '.1 submit recommended changes to the Chairman of the-Managenint Safety Review Committee.
'i.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Management Safety Review Committee.
AUTHORITY 6.5.1.7 The Plant Review Committee shall:
a.
Recommend to the Plant Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Render: determinations in writing with regard to whether or 3
not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
c.
Provide immediate written notification to the Chairman of the Management Safety Review Committee of disagreement between the
'?RC and the Plant Superintendent; 'h'owever, the' Plant Superin-tendent shall have responsibility for resolution of such dis-agreements pursuant to 6.5.1.1 above.
RECORDS 6.5.1.8 The Plant Review Committee sha11' maintain written minutes of each m'eeting and copies shall be provided to the Plant _ Superintendent and'the Chairman of the Management Safety Review Committee.
6-7 Amendment 30 l
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i, ADMINISTRATIVE CONTROLS 6.5.2 MANAGEMENT SAFETY REVIEW COM!!ITTEE (!!SRC)
FUNCTION-6.5.2.1-The Management Safety Review Committee shall function to provide independent review'and audit of designated activities in the areas of:
a.
nuclear power plant operations
. b.
nuclear engineering c.
chemistry and radiochemistry 3
d.
metallurgy e.
instrumentation.and control f.' radiological safety g.
mechanical and electrical engineering h.
quality assurance practices J
6-8 Amendment 30
r ADMINISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The MSRC shall be composed of the:
Assistant General Manager and Chief Engineer - Chairman Technical Assistant - Secretary Manager, Engineering Department Assistant General Manager, Operations Manager, Nuclear Operations Supervising Nuclear Engineer
-Manager, Generation Engineering Quality Assurance Director
. Quality Assurance Engineering ALTERNATES' 6.5.2.3' Alternate members shall be appointed in writing by the MSRC Chairman to serve on a temporary basis; however, no more than two alternatives shall
-participate in MSRC activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the MSRC Chairman
'to provide expert advice to the11SRC.
MEETING FREQUENCY 6.5.2.5 The'MSRC shall meet at least once per calendar quarter during the initial year of facility operation following fuel loading and at least once per six months thereafter.
QUORUM 6.5.2.6 A quorum of MSRC shall consist of the Chairman or his designated alternate and a majority of the MSRC members including alternates.
No more than a minority of the quorum shall have line responsibility for operation
.of the facility.
6-9 Amendment 30
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ADMINISTRATIVE CONTROLS' RE'IEWL V
6.5.2.7 The MSRC shall review:
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.
d.
Proposed ~ changes in Technical Specifications or licenses.
3 e.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures-or instructions having nuclear safety significance.
- f. 'Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear
-rafety.
g.
ABNORMAL OCCURRENCES, as defined in Section 1.8 of these Technical Specifications.
h.
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or Components.
1.
Reports and meeting minutes of the Plant Review Committee.
4 s
4 6-10 Amendment 30
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. ADMINISTRATIVE'CO?:TROLS AUDITS
'6.5.2.8. Audits of-facility activities shall be performed under the cognizance of the.MSRC.
These audits shall encompass:
The conformance of. facility operation to all provisions a.
~ contained within the Technical Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
c.
The results of all' actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
- d.,The performance of all activities required by the Quality 3
Assurance Program to meet the criteria of Appendix "B",
10 CFR 50, at least once per two years, The Facility Emergency Plan and implementing procedures at e.
least once per two years.
f.
The Farility Security. Plan and implementing procedures at least once pcr two years.
-g.
Any other area of facility operation considered appropriate by the MSRC or the General Manager.
AUTHORITY 6'.5.2.9 The MSRC shall report to and advise the General Manager on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
6-11 Amendment 30
l ADMINISTRATIVE CONTROLS RECORDS
'6.5.2.10 Records of MSRC activities shall'be prepared, approved, and
-distributed as indicated below:
a.
Minutes of each MSRC meeting shall be prepared, approved and forwarded to the General Manager within 14 days following each meeting.
-b.'
Reports of reviews encompassed by Section 6.5.2.7 e, f, g, and h above, shall be prepared, approved and forwarded to the General Manager within 14 days following completien of the review.
3 c.
Audit reports encompassed by Section 6.5.2.8 above, shall be forwarded to the General Manager and to the mar.agement positions responsible for the areas audited within 30 days after completion of the audit.
6.6 ABNORMAL OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of an ABNORMAL OCCURRENCE:
a.
The Commission shall be notified and/or a report submitted pursuant to the requirements of Specification 6.9.
)
b.
Each Abnormal Occurrence Report submitted to the Commission shall be reviewed by the PRC and submitted to the MSRC_and the Plant Superintendent.
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6-12 1
Amendment 30 s
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< ADMINISTRATIVE-CONTRdLS 6.7: SAFETY LIMIT VIOLATION-6.~ 7.1
- The following actions 'shall be taken in the event a Safety Limit -
-is: violated:
L a'.. The' provisions of~10 CFR-50.36 (c) (1) (1) shall be complied
~
with immediately.
b.
- The Safety Limit violation = hall be reported to the Plant Super-
. intendent,. the Chairman oflthe MSRC and to the Commission immed-iately.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be' reviewed by the PRC. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems.or structures,-
- and (3) corrective acetion taken to-prevent recurrence.
i d.
The Safety Limit Violation' Report shall be submitted to the Commission, the MSRC and the Plant Superintendent within 10
~
days of the violation.
J
' 6. 8 PROCEDURES 6.8.1 L'ritten procedures and administrative policies shall be established, implementec-cud maintaim d that neet or exceed the requirements'and recommen-3
-dations of Section 5.1 and 5.3 of ANSI-N18.7-1972 and Appendix "A" of USAEC
' Regulatory Guide 1.33 except as provided in.6.8.2 and 6.8.3 below.
- 6.8.2J Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed by:the PRC and approved by the Plant Superintendent o
prior to. implementation and periodically'as' set-forth in each document.
- 6. 8. 3 :
Temporary changes:to procedures of 6.8.1 above may be made provided:
z v-a.
The intent of th original. 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 Reactor Operator's License on'the unit affected.
~
'c.
The. change is documented, reviewed by the PRC, and approved by1the Plant Superintendent within 7 days of implementation.
6.
Amendment 30
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ADMINISTRATIVE CONTROLS 6.9-REPORTING REOUIREMENTS ROUTINE AND ABNORMAL OCCURRENCE REPORTS 6.9.1 Information to be reported to the Commission, in addition to the reports required by Title 10, Code of Federal Regulations, shall be in accordance with the Regulatory Position in Revision 2 of Regulatory Guide 1.16* " Reporting of Operating Information - Appendix "A" Technical Specifi-
. cations."
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Regulatory Operations Regional Office within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirements of-the applicable reference specification:
A.
Startup Report A summary report of unit startup and power escalation testing and an evaluation of the results from these test programs shall be submitted within 60 days following commencement of commercial power operation. The test results shall be compared with design predictions and specifications.
39 B.
First Year Operation Report A report shall be submitted within 60 days after completion of the first year of commercial power operation.
This report may be incorporated into the semi-annual operating report and shall cover the following:
1.
An evaluation of unit performance to date in comparison with design predictions and specifications; 2.
A reassessment of the safety analysis submitted with the license application in light of measured operating charac-teristics when such measurements indicate that there may be substantial variance from prior analyses; 3.
An assessment of the performance of structures, systems and components important to safety:
4.
A progress and status report on any items identified as requiring additional information during the operating license review or during the startup of the plant, including items discussed in the AEC's safety evaluation, items on which additional information was required as conditions of the license and items identified in the licensee's startup report.
- Exceptions noted on letter to A. Giambusso December 10, 6-14
-1974 concerning Amendment 30.
Amendment 30
' ADMINISTRATIVE CONTROLS' C.-
A Reactor Building structural integrity report shall be submitted within 90 days of completion of each of the following tests covered by Technical Specification 4.4.2* (the integrated leak rate test is covered in Technical Specification above).
- l.. Annual Inspection 2.
Tendon stress surveillance 3.
End anchorage concrete surveillance 4.
Liner plant surveillance
'D.
Inservice inspection program.
6.10
-RJCORD RETENTION 3Z
'6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal =:intenance cetivitics, inspections, repair and replacement of principal items of equipment rel'ated to nuclear safety.
c.
ABNORMAL OCCURRENCE Reports, d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments, f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
1.
Records of annual physical inventory of all source material of 4
. record.
6.10.2 The following records shall be retained for the duration of the
-Facility Operating License:
a.
Record and.draving changes reflecting facility design modifi-cations made to systems and equipment-described in the Final Safety' Analysis Report.
[
6-15 l:
Ad.endr.ent 30 s
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MINISTRATIVE CONTROLS b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup hir, tories.
c.
Records of facility radiation and contamination surveys.
d.
Records of radiation exposure'for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility-
. components designed for a limited number of transients or cycles.
g.
Records of training and qualification for current members of the plant operating staff.
h.
Records of.in-service inspections performed pursuant to these Technical Specifications.
1.
. Records of Quality Assurance activities required by the QA Manual.-
- j. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
- k.. Records of meetings of the PRC and the MSRC.
3) 6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 RESPIRATORY PROTECTION PROGRAM l
ALLOWANCE 6.12.1 Pursuant to 10 CFR 20.103(c) (1) and (3), allowance may be made for the use of respiratory protective equipment in conjunction with activities authorized by the operating' license for this facility in deter-mining whether individuals in restricted areas are exposed to concentrations in excess of the-limits specified in Appendix B, Table I, Column 1, of 10 CFR-20, subject to the following conditions and limitations.
a.
~ The limits provided in Section 20.103 (a) and (b) shall not be exceeded.
j i
6-16 Amendment 30 s
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I-4 ADMINISTRATIVE COWIROLS IALLOWANCE-(Continued) ib.
.If the radioactive. material is of such form that intake through the skin or other additional route is-likely, individual exposures to radioactive material shall be controlled so that the radioactive content.of any'eritical organ from all routes of' intake' averaged overl7. nnsecutive days does not. exceed that which would result from inhaling such radioactive material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the per-tinent concentration values provided in Appendix B, Table I, Column-1, of 10 CFR_20.
c.
.For radioactive materials designated "Sub" in-the " Isotope" column of Appendix B, Table I, Column 1 of 10 CFR 20, the concentration
[
.value specified shall.be based upon exposure to the material as an external. radiation source. _ Individual exposures to these mat-erials shall be accounted for as part of the limitation on individ-ual dose in 520.101.
These materials shall be subject to applicable l
. process and other engineering controls.
PROTECTION PROGRAM 6.12.2 In all operations in which adequate limitation of the inhelation of radioactive material by the use of process or other engineering controls is
. impracticable, the licensee may permit an individual in a restricted area to
-use respiratory protective ' equipment to limit the inhalation of airborne radioactive material, provided:
a.
The limits specified in 6.12.1 above, are not exceeded.
b.
Respiratory protective equipment is selected and used so that the peak concentrations of airborne radioactive material. inhaled 1
by'an individual wearing-the equipment do not exceed the pertin-ent. concentration values specifieduin Appendix B, Table I,. Column j-
.1, of 10 CFR 20.
For the purposes of this subparagraph, the concentration of-radioactive material that is inhaled when res-pirators are worn may be determined by dividing the ambient air-borne concentration by the protection factor specified in Table 6.12-1 for the respirator protective equipment worn.
If the intake of radioactivity is later determined by other measure-
.ments to-have been different than that initially estimated, the later. quantity shall be used in evaluating the exposures.
c.
The licensee' advises-each respirator user that be may leave the area at any time for relief from respirator use in case of equip-F Lment malfunction,' physical or psychological discomfort, or any other condition that~might cause reduction in the protection afforded the wearer.
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- d.. The licensee maintains a respiratory protective program adequqce to assure that the requirements above are met and incorporates 17 Amendment 30 4
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i ADMINISTRATIVE CONTROLS 6.13 HIGH RADIATION AREA 6.13.1
.In lieu of the " control device" or " alarm signal" required by para-graph 20.203 (c) (2) of 10 CFR 20:
5 Each High Radiation Area in which the intensity of radiation is a.
greater than 100 mren/hr.but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area
-and entrance thereto shall be controlled by issuance of a Radia-tion Work Permit and any individual or group of individuals E
permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
.b.
Each High Radiation Area in which the intensity of radiation is greater than 1000 mrem /hr shall be subject to the provisions of 6.13.1(a) above, and in' addition locked doors shall be provided
.to prevent unauthorized entry into such area and the keys shall be maintained under the administrative control of the Shift Supervisor on duty.
l 6-19 i
l Amendment 30 i
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TABLE 6.9-1 PROTECTION FACTORS FOR RESPIRATORS PROTECTION FACTORSZ GUIDES TO SELECTION OF EQUIPMENT PARTICULATES AND BUREAU OF MINES APPROVAL SCllEDULES*
VAPORS AND CASES FOR EQUIPMENT CAPAllLE OF PROVIDING A EXCEPT TRITIUM LEAS'1 EQUIVALENT PROTECTION FACTORS DESCRIPTION MODESI 3
OXIDE
- cr schedule superseding for' equipment of type listed I.
AIR PURIFYING RESPIR*. TORS Facepiece, half-mask7 NP 5
21B 30 CFR S 14.4(b)(4)
Facepiece, fu117 NP 100 21B 30 CFR S 14.4(b)(5); 14F 30 CFR II. ATMOSPilERE-SUPPLYING RESPIRATOR y
1.
Airline respirator y
Facepiece, half-mask CF 100 19B 30 CFR S 12.2(c)(2) Type C (1)
Facepiece, full CF 1,000 19B 30 CFR S 12.2(c)(2) Type C (i) 7 Facepiece, fu11 D
100 19B 30 CFR S 12.2(c)(2) Type C (ii)
Faceplece, full PD 1,000 19B 30 CFR : '2.2(c)(2) Type C (iii) llood CF 5
6 Suit CF 5
6 2.
Self-contained breathing aEparatus (SCIIA) 7 Facepiece, full D
100
'13E 30 CFR 5 11.4(b)(2) (i)
Facepiece, full PD 1,000 13E 30 CFR 5 11.4(b)(2) (ii) f Facepiece, full R
100 13E 30 CFR S 11.4(b)(1) 8.
f III. COMilINATION RESPIRATOR Any combination of air-Protection factor 19B CFR 5 12.2(e) or applicable o
purifying and atmosphere-for type and mode Schedules as listed above supplying respirator of operation as listed above
[These notes are on the following pages]
1, 7,
3, 8#,
5, 6,
7 u
f TABLE 6.9-1 (Continued)
- See the'following symbols:
CF: ~ continuous flow D:
demand NP:. negative pressure (i.e., negative phase during inhalation)
PD:
pressure demand (i.e., always positive pressure)
R:
recirculating (closed circuit) 2 (a).For purposes of'this-specification the protection factor is a
' measure of the degree of protection afforded by a respirator, defined'as the ratio of the concentration of airborne radio-active material outside the respiratory protective equipment to that inside the equipment (usually inside the.facepiece) under conditions of use.
It is applied to the ambient air-borne concentration to estimate the concentration inhaled by the wearer according to the following formula:
Concentration Inhaled = Ambient Airborne Concentration Protection Factor (b) The protection factors apply:
(i) only for trained individuals wearing properly fitted respirators used.and.maint.ained.mnder.suyervision in a well-planned respiratory protective progtaa.
3?
(ii) for air-purifying respirators only when high efficiency
[above 99.9% removal efficiency by U. S. Bureau of Mines type dioctyl phthalate (DOP) test] particulate filters and/or sorbents appropriate to the hazard are used in atmospheres not deficient in oxygen.
(iii) for atmosphere-supplying respirators only when supplied with adequate respirable air.
3 Excluding radioactive contaminants that present an absorption or sub-mersion hazard.
For tritium oxide approximately half of the intake occurs by absorption through the skin so that an overall protection factor of not more than approximately 2 is appropriate when atmosphere-supplying respirators are used to protect against tritium oxide.
Air-purifying respirators-are not recommended for use against tritium oxide.
See also footnote 5, below, concerning supplied-air suits and hoods.
Under chin type only.
Not recommended for use where it might be possible
'for the ambient airborne concent*ation to reach instantaneous values greater than~50 times the pertinent vol"es in Appendix B, Table I, Column 1 of 10 CFR Part 20.
6-21 Amendment 30 s.
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TABLE 6.9-1 (Continui )
d
- 5l Appropriate protection factors must be determined taking account of
~
the design of the suit or hood and its permeability to the contaminant under conditions'of use.
No protection factor greater then 1,000 shall be used except as authorized by the Commission.
6 No approval schedules currently available for this equipment.
Equip-ment must be evaluated by testing or on basis of available test infor-mation.
7 only for shaven faces.
NOTE 1: Protection. factors for respf ators, as may be approved by the U.S. Bureau of Mines accorting to approval schedules for respirators to protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors g
listed in this Table.
The protection factors in this Table may not be appropriate to circumstances where chemical or_other respiratory hazards exist in addition to radioactive hazards.
The selection and use of respirators for such circumstances should take into account approvals of the U.S. Bureau of Mines in accor-dance with its applicable schedules.
- NOTE 2: Radioactive contaminants for which the concentration values in Appendix B, Table I of this part are based on internal dose due 4
to inhalation may, in addition, present external exposure hazards at higher concentrations. Under such circumstances, limitations on occupancy may have to be governed by external dose limits.
6-22 Amendment 30 v
=
- RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting. Conditions for Operation L
3.5.2.7 The' control rod' drive. patch panels shall be locked at all times with limited i
access to' be -authorized by the superintendent' or his designated representative. l Bases I
The power-imbalance envelope defined in figure 3.5.2-2 is based on LOCA analyses which have defined the maximum linear heat rate (see figure 3.5.2-3) suci that the maximum
. clad temperature will not exceed the Interim Acceptance Criteria.
Operation outside
-of the power imbalance envelope alone does not constitute a situation that would cause the Interim Acceptance. Criteria to be exceeded should a LOCA occur.
The power imbalance envelope represents the boundary of operation limited int the Interim Acceptance Criteria
~
only if.the control rods are at the position limits as defined by figure 3.5.2-1 and if a 4 percent quadrant power tilt exists.
Additional conservatism is introduced by 4
application of:
A.
Nuclear uncertainty factors.
B.
Thermal calibration uncertainty.
C.
Fuel densification effects.
D.
Hot rod manufacturing tolerance factors.
i
~
The 30 percent overlap between successive control rod groups is allowed since the worth of a. rod is~ lower at the upper and lower part of the stroke.
Control rods are arranged in groups or banks defined as follows:
B Group Function 1
Safety 2
Safety i
3 Safety-4' Safety 5
Regulating 6
Regulating 7
Regulating 8
APSR-(axial power shaping bank)
Control rod groups'are withdrawn in sequence beginning with group 1.
Group 5 is overlapped 25 percent with groups 6 and 7, which operate in parallel. The normal position at power is for groups 6 and 7 to be partially inserted.
The1 minimum available rod worth provides for achieving hot shutdown by reactor.
~
. trip.at any' time. assuming the highest worth control rod remains'in the full out s position. '(1) l Inserted rod groups:during power operation will not contain single rod worths
. greater than 0.65 percent ak/k.' This value has been shown to be safe by'the safety analysis of the hypothetical' rod ejection accident. (2) A single inserted
~
control rod worth of 1~.0 percent ak/k'at beginning of life, hot, zero power would result in the'same tr'nsient peak thermal power and therefore the same a
environmental consequences as a 0.65 percent Ak/k ejected rod worth at rated
. power.
4 Amendment 30 3-33a t
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.g-TABLE 3.5.1-1 (Concluded)
INSTRUMENTS OPERATING CONDITIONS (A)
(B)
Minimum Operab]c.
Minimum Degree Operator ~ Action if Conditions of Functional Unit Channels of Redundancy Columns A and B Cannot be Met Safety Features *
'4.
Reactor Building spray valve a.
Reactor. Building pres-2 1
Bring to hot shutdown sure instrument channel within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> N
b.
Manual Pushbutton 2
1 Bring to hot shutdown g
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> d
Process Instrumentation o
1.-
Pressurizer Level 2
N.A.
Bring to hot shutdown h
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 30 c) o H
- 1f minimum conditions are not met within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />' after hot shutdown, the unit shall be placed in f
a cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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