ML20077K855
| ML20077K855 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/30/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077K858 | List: |
| References | |
| NUDOCS 9108090156 | |
| Download: ML20077K855 (9) | |
Text
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ENTERGY OPERATIONS, INC.
SYSTEH ENERGY RESOURCES, INC.
SOUTH MIS $1551PP1 ELECTRIC POWER ASSOCIATION MISSISSIPPI POWER AND LIGHT COMPANY DOCKET NO. 50-416 GRAND GULF NUCLEAR STATION, UNIT 1 APENDMENTTOFACILITYOPERATINGLICElg Amendment No. 80 License No. NPF-29 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 11, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicabic requirements have been satisfied.
91080701D6 910730 PDR ADUCK ObOOO416 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license anendnienti I
arid paragraph 2.C.(2) of facility Operating License No. NPf-29 is hereby anended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmentel Protection Plan contained in Appendix B, as revised through Amendment No. 80, are hereby incorporated into this license.
Entergy Operations, Inc. shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f
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Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical-Specifications Date of issuance: July 30,1991 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 80 FACILITY OPERATING LICENSE NO. NPF-29 DOCKET NO. 50-416 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also included to maintain document completeness.
REMOVE PAGES INSERT PAGES 3/4 7-11 3/4 7-11 6-14 6-14 6-1$
6-15 6-19 6-19
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PLANTSYSTEM)
SURVEILLANCE REQUIREMENTS (Continued)
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e.
Functional Tests During the first refueling shutdown and at least once per 18 months f
thereafter during shutdown, a representative sample of. snubbers shall be tested using one of the following sample plans for each type of snubber. The sample plan shall be selected prior to the test period and cannot be changed during the test period. A written report of the sample I,lan selected shall be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR Part 50 prior to the test period or the sample plan used in the prior test period shall be implemented:
1)
At least'10% of.the total of each type of snubber shall be functionally tested either in-place or in a bench test.
For each snubber of a type that does not meet the functional test acceptance criteria of Specification 4.7.4.f, an additional 5%
of that type of snubber shall be functionally tested until no more failures are '.nd or until all snubbers of that type have been functionally tested; or 2)
A representative sample of each type of snubber shall be func-tionally tested in accordance with figure 4.7.4-1.
"C" is the total number of snubbers of a type found not' meeting the accept-l ance-requirements of Specification 4.7.4.f.
The cumulative num-ber of snubbers of a type tested is denoted b At the end
?
-of each day's testing, the new values of "N" y "N".and "C" (previous day's total plus current day's increments) shall be plotted on Figure 4.7.4-1.
If at any time the point plotted falls in the
" Accept" region, testing of snubbers of that type may be termi-When the_ point plotted lies in the " Continue Testing"il nated.
additional snubbers of that type shall be tested unt region thepoIntfallsinthe" Accept"regionorallthesnubbersof that-type have been tested.
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GRAND GULF-UNIT 1 3/4 7-11 Amendment No.80 L
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ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION (Continued) c.
The Safety Limit Violation Report shall be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR Part 50, the SRC and the Vice President, Operations GGNS within 14 days of the violation.
r d.
Critical operation of the unit shall not be resumed until authorized by the Commission.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below, a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978, b.
Refueling operations, c.
Surveillance and test activities of safety related equipment.
d.
Security Plan 'raplementation.
e.
Emergency Plan implementation, f.
Fire Protection Program implementation, g.
PROCESS CONTROL PROGRAM implementation, h.
OffSITE 00SE CALCULATION MANUAL implementation.
1.
Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 4.15, February 1979.
6.8.2 Each procedure of 6.8.1 above, and changes thereto, shall be reviewed as required by 6.5, above, prior to implementation and shall be reviewed periodically as set forth in administrative procedures.
6.8.3 The following programs shall be established, implemented, and maintained:
a.
Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels.
The systems include the:
1.
RCIC system outside containment containing steam or water, except the drain line to the main condenser.
2.
RHR system outside containment containing steam or water, except the line to the LRW system and headers that are isolated by manual valves.
3.
HPCS system.
4.
LPCS system.
5.
Hydrogen analyzers of the combustible gas control systen.
GRAND GULF-UNIT 1 6-14 Amendfrent No. 80
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.
Feedwater leakage control system.
7.
Post accident sampling system.
8.
Suppression pool level detection portion of the suppression pool makeup system.
The program shall include the following:
1.
Preventive maintenance and periodic visual inspection requirements, and 2.
Integrated leak test requirements for each system at refueling cycle intervals or less, b,
In-Plant Radiation Monitorina A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions.
This program shall include the following:
1.
Training of personnel, 2.
Procedures for monitoring, and 3.
Provisions for maintenance of sampling and analysis equipment.
c.
Post-accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gasenus effluents, and containment atmosphere samples under accident conditions.
The program shall include the following.
1.
Training of personnel.
2.
Procedures for sampling and analysis, 3.
Provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REQUIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10 Code of Federal Regulations, the following reports shall be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 of 10 CFR Part 50.
STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license. (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.
GRAND GULF-UNIT 1 6-15 Amendment No.80
ADM!h151RATIVE CONTROL 5 STARTUP REPORTS (Continued) 6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a compari-son of these values with design preriictions and specifications.
Any correc-tive 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.
6.9.1.3 Startup report: shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 deys following resumption or comencement of commercial power operation, or (3) 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 resumptier, or comtencement of commercial operatien, supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUAL REoDRTSE 6.9.1.4 Annual reports cuering the activities of the unit as described belo.
for the r evious calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year fol-lo.ing initial criticality.
6.9.1.5.1 Reperts shall ir.clude a tabulation on an annual basis of the number l of station, utility, and other personnel, including contractors, receiving exposures greater than 100 mrem /yr and their associated manrem exposure ac-cordingtoworkandjobfunctions,SI e.g., reactor operations and surveil-lance, in ervice inspection, routine maintenance, special maintenance (cescribe maintenance), waste processing, and refulling.
The dose assignments to various duty functions tray be estimated based o1 pocket dnsimeter, TLD, or film badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be accounted foa, in the aggregate, at least 60 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
6.9.1.5.2 Reports shall include documentation of all challenges to safety and relief valves.
6.9.1.5.3 Reports shall include the results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.5.
The fol-lowing information shall be included:
(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while the limit was exceeded, and.csults of one analysis after the radiciodine activity was reduced to less than the limit M single submittal may be made for a multiple unit station.
A The submittal should-combine those sections that are common to all units at the station.
S This tabulation supplements the requirements of $20.407 of 10 CFR Part 20.
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GRAND GULF UNIT 1 6-16 AmendmentNo.28l l
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ADMINISTRATIVE CONTROLS 5_EMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT (Continued)
Principal radionuclide (specify whether determined by measurement or c.
estimate),
d.
Type of waste (e.g., spent resin, compact dry waste, evaporator bottoms),
Type of conteiner (e.g., LSA, Type A, Type B, Large Quantity), and e.
f.
Solidification agent (e.g., cement, urea femaldehyde).
The radioactive effluent release reports shall include unplanned releases from the site to the UNRESTRICTED AREA of radioactive materials in gaseous and liquid effluents on a quarterly basis.
Theradioactiveeffluentreleasereportsshallincludeanychangestothe PROCESSCONTROLPROGRAM(PCP)Ingthereportingperiod.
0FFSITE DOSE CALCULATION WsNUAL s0DCH) or radio-active waste systems made dur HONTHLY OPERATING REPORTS 6.9.1.10 Routine reports of operating statistics and shutdown experience includingdocumentationofallchallengestomainsteamsystemsafety/rellef valves, shall be submitted on a monthly basis no later than the 15th of each l
month following the calendar month covered by the report.
SPECIAL REPORTS 6.9.2 Special reports sh
,1 be submitted to the Nuclear Regulatory Commission pursuant to Section 50.4 (
10 CFR Part 50 within the time period specified for each report.
6.10 RECORD RETENTION In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least five years:
a.
Records and logs of unit operation covering time interval at each power level, b.
Records and logs of principal maintenance activities, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
GRAND GULF-UNIT 1 6-19 Amendment No.80
Aeg!N1$TRAT!vt CONTROLS 6.10 RECORD RETENTION (Continued)
RecoIds of surveillance activities, inspections and calibrations d.
required by these Technical Specifications, Records of changes made to the procedures required by Specification e.
6.4.1.
f.
Records of radioactive shipments, g.
Records of sensed source and fission detsetor leak tests and results.
h.
Records of annual physical inventory of all sealed source material of record.
j 6.10.2 The following records shall be retained for the duration of the Unit Operating License:
I Records and drawing changes reflecting unit design modifications made a.
to systems and equipment described in the Final Safety Analysis Repert, b.
Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories, Records of radiation exposure for all individuals entering radiation c.
control areas.
d.
Records of gaseous and liquid radioactive material released to the environs.
Records of transient or operational cycles for those unit costponents e.
identified in Table 5.7.1-1.
f.
Records of reactor tests and experiments.
g.
Records of training and qualification for current eescers of the unit staf*.
h.
Records of in service inspections performed pursuant to these Technical Specifications.
1.
Records of Quality Assurance activities required by the Operational Quality Assurance Manual not Itsted in Section 6.10.1.
l j.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experfaents pursuant to 10 CFR 50.59.
k.
Records of meetings of the PSRC and the SRC.
1.
Records of the service lives of all hydraulic and rechanical snubbers including the date at which the service life consnences and associated installation and maintenance records, Records of analyses required by the radiological environmental s.
monitoring program.
GRAND GULF-UNIT 1 6 20 Amendment No.21
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