ML20087Q011

Proposed Tech Specs Adding New Fuel Type MAPLHGR Curve & Changing Min Critical Power Ratio Curves for 8x8R & P8x8R Fuel to Support Reload 4 Core Design & Allowing Hybrid I Control Rod Assembly Operation

ML20087Q011
Person / Time
Site:	Hatch
Issue date:	04/03/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20087Q008	List: ML20087Q007 ML20087Q011
References
TAC-54169, TAC-54607, NUDOCS 8404100205
Download: ML20087Q011 (13)

Text

I l

GeorgiaPower\h ATTACIMENT 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HA'ICH NUCIEAR PIANT UNIT 2 REQUEST 'IO CHANGE TECHNICAL SPECIFICATIONS FOURTH CORE RELOAD PROPOSED 'IECHNICAL SPECIFICATIONS REVISIONS

'Ihe Technical Specifications for Plant Hatch Unit 2 are proposed for revision as presented in this section. Below is a table which provides instructions for incorporating the revisions.

If the Technical Specification revisions are accepted as proposed, the HNP-2 Technical Specifications (Appendix A to Operating License NPF-5) should be incorporated as follows:

Deletions Insertions Applicable Significant Iten (Page) (Page) Hazards Evaluation Section(s) 1 3/4 2-1 3/4 2-1 1 3/4 2-2 (overleaf) 3/4 2-2 (overleaf) 3/4 2-4f (overleaf) 3/4 2-4f (overleaf) 2 ---

3/4 2-49 1 3/4 2-7 (overleaf) 3/4 2-7 (overleaf) 3 3/4 2-7a 3/4 2-7a 2 3/4 9-3 (overleaf) 3/4 9-3 (overleaf) 4 3/4 9-4 3/4 9-4 4 5 B 3/4 9-1 B 3/4 9-1 4 B 3/4 9-2 (overleaf) B 3/4 9-2 (overleaf) 6 5-3 5-3 3 5-4 (overleaf) 5-4 (overleaf) i S

PDR 700775

3/4.2 POWER DISTRIBtJTION LIMITS 3/4.2.1 AVERAGE PIANAR LINEAR HEAT GENERATION RATE LIMITING CONDITION FOR OPERATION 3.2.1 ALL AVERAGE PIANAR LINEAR HEAT GENTRATION RATES (APulGRs) for each type of fuel as a function of AVERAGE PLANAR EXPOSURE shall not exceed the limits shown in Figures 3.2.1-1 through 3.2.1-9. l APPLICABILITY: CONDITION 1, when THER%L POER 2 25% of RATED 'IhEINAL PChTR.

ACTION:

With an APLHGR exceeding the limits of Figures 3.2.1-1 through 3.2.1-9, l initiate corrective action within 15 minutes and continue corrective action so that APLHGR is within the limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 25% of RATED THEBMAL PGER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SURVEILULNCE REQUIREMENTS 4.2.1 All APLHGRs shall be verified to be equal to or less than the applicable limit determined fran Figures 3.2.1-1 through 3.2.1-9: l

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Whenever THERMAL POWER has been increased at least 15% of RATED THERMAL PGER and steady state operating conditions have been established, and

c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with a LPIITING CONTROL ROD PATTERN for APLHGR.

HATOI - UNIT 2 3/4 2-1

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3/4.2.3 MINIMUM CRITICAL POWER RATIO S URVEILLANCE REOUIREMENTS (Continued) h

b. t as defined in Specification 3.2.3; the detennination of t e limit must be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram time surveillance test requir'ed by Specification 4.1.3.2.

- MCPR shall be* determined to be equal to or greater than the applicable

- limit:

a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,

b. Whenever THERMAL POWER has been in' creased by at least 15% of RATED THERMAL POWER and steady state operating conditions ' have been established, and

c. Initially and at least once per 12' hours when the reactor i~s operating with a LIMITING CONTROL R0D PATTERN for MCPR.

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. HATCH.- UNIT 2 3/4 2-7a Amendment No.

.e

REFUELING OPERATIONS

(,, .

3/4.9.2 INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.9.2 At least 2 source range monitor * (SRM) channels shall be OPERABLE and inserted to the normal operating level:

a. Each with continuous visual indication in the control room,

b. At least one with an audible alarm in the control room,

c. One of the SRM detectors located in the quadrant where CORE ALTERATIONS are being pe'rformed and the other SRM detector located in an adjacent quadrant, and

d. The " shorting links" removed from the RPS circuity during CORE ALTERATIONS and shutdown margin denonstrations.

APPLICABILITY: CONDITION 5.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS ** or positive reactivity changes and act9 ate the manual scram. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.2 Each of the above required SRM channels shall be demonstrated OPERABLE by:

a; At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />;

1. Performance of a CHANNEL CHECK,

2. Verifying the detectors are inserted to the normal operating level,

3. During CORE ALTERATIONS, verifying that the detector of an OPERABLE SRM channel is located in the core quadrant where CORE ALTERATIONS are being performed and one is located in the adjacent quadrant.

• The use of special movable detectors during CORE ALTERATIONS in place of the normal SRM nuclear detectors is permissible as long as these special detectors are connected to the normal SRM circuits.

• • Except movement of SRM or specisi movable detectors.

HATCH - UNIT 2 3/4 9-3

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INSTREMENT .. ION SURVEILIANCE REQUIREMENIS CDNTINUED b'. Performance of a CHANNEL EUNCTIONAL TEST:

1. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to the start of CORE ALTERATIONS, and

2. At least once per 7 days.

c. Verify that the channel count rate is at least 3 cps at least once per - 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during CORE ALTERATIONS, and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, except:

1. The 3 cps is. not required during core alterations involving only fuel unloading provided the SINS were confirmed to read at least 3 cps initially and were checked for neutron response.

2. 'Ihe 3 cps is not rajuired initially on a full core reload.

Prior to the reload, up to four fuel assenblies will be loaded l into their previous core positions next to each of the 4 SIEs to obtain the rsauired count rate.

d. Verifying that the RPS circuitry " shorting links" have been renoved and that the RPS circuitry is in a non-coincidence trip mode within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to starting 00RE AL'IERATIONS or shutdown margin denonstrations.

i HA'ICII - UNIT 2 3/4 9-4

3/4.9 REFUELING OPERATIONS BASES 3/4.9.1 REACIOR MODE SWI'IGI Iocking the OPERABLE reactor mode switch in the refuel position ensures that the restrictions on rod withdrawal and refueling platform movment during the refueling operations are properly activated. These conditions reinforce the refueling procedures and reduce the probability of inadvertent criticality, dmage the reactor internals or fuel assablies, and exposure of personnel to excessive radioactivity.

3/4.9.2 INSTRENENTATION

%e OPERABILITY of at least two source range monitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core. During the unloading, it is not necessary to maintain 3 cps because core alterations will involve only reactivity rmoval and will not result in criticality. %e loading of up to four bundles around the SBMs before attaining the 3 cps is permissible because these bundles were in subcritical configuration when they were reoved and therefore will reain subcritical when placed back in the previous positions.

3/4.9.3 CONTROL ROD POSITION

%e rquirment that all control rods be inserted during CORE ALTERATIONS ensures that fuel will not be loaded into a cell without a control rod and prevents two positive reactivity changes frm occurring simultaneously.

3/4.9.4 DECAY TIME

%e minimm rquirement for reactor suberiticality prior to _ fuel movment ensures that sufficient' time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assmptions used in the accident analyses.

3/4.9.5 SECONDARY CDNTADNENT Secondary containment is designed to minimize any ground level release of radioactive material which may result fr m an accident. The reactor building provides secondary contaiment during normal operation when the drywell is sealed and in service. When the reactor is shutdown or during refueling, the drywell may be open and the reactor building then becmes the primary contaiment. %e refueling floor is maintained under the secondary contaiment integrity of Hatch-Unit 1.

Establishing and maintaining a vacuum on the building with the standby gas treatment systs once per 18 months, along with the surveillance of the doors hatches and dampers, is adequate to ensure that there are no violations of the integrity of the secondary containment. Only one closed damper in each penetration line is rq uired to maintain the integrity of the secondary containment.

UNICI - UNIT 2 B 3/4 9-1

4 REFUELING OPERATIONS BASES 3f4.9.6 COMUNICATIONS The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facility status or core reactivity condition during movement of fuel within the reactor pressure vessel.

3/4.9.7 CRANE AND HOIST OPERABILITY The OPERABILITY requirements of the. cranes and hoists used for movement of fuel assemblies ensures that: (1) each has sufficient load capacity to lift a fuel element, and (2) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.8 CRANE TRAVEL-SPENT FUEL STORAGE POOL The restriction on movement of loads in excess of the nominal weight of a' fuel element over irradiated fuel assemblies ensures that no more than the contents of one fuel assembly will be ruptured in the event of a fuel handling accident. This assumption is consistent with the activity release assumed in the accident analyses. .

3/4.9.9 and 3/4.9.10 WATER LEVEL-REACTOR VESSEL AND WATER LEVEL-SPENT F STORAGE POOL The restrictions on minimum water le' vel ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. This minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.11 CONTROL ROD REMOVAL

- This specification ensures that maintenance or repair of control rods er control rod drives will be performed under conditions that limit the probability of inadvertent criticality. The requirements for simultanehus removal of more than one control rod are more stringent since the SHUTDOWN MARGIN specification provides for the core to remain subcritical with only one control rod fully withdrawn.

HATCH UNIT 2 B 3/4 9-2

(_

! DESIGN FEA'IURES, CIN1 POL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 137 cruciform-shaped control rod assablies.

5.4 REACIOR 000I1NI' SYSTB4 DESIGN PRESSURE AND TEMPERA'IURE 5.4.1 The reactor coolant systs is designed and shall be maintained:

a. In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for no,rmal degradation pursuant to the applicable Surveillance Requirements,

b. For a pressure of 1250 psig, and

c. For a taperature of 5750F YOLtNE 5.4.2 The total water and steam volme of the reactor vessel and recirculation system is approximately 17,050 cubic feet at a nminal Tave of 5400F.

5.5 METEOROIDGICAL 'ICWER IOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.1-1.

5.6 EUEL S'IORAGE CRITICALITY 5.6.1 The new and spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a keff equivalent to 0.95 when flooded with .unborated water. The ~ keft of 0.95 includes conservative allowances for uncertainties.

HA'ICH - UNIT 2 5-3

DESIGN FEATURES OPAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevatic:1185 feet.

CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2845 fuel assemblies. l FUEL STORAGE ,

5.6.4 Fuel in the Spent Fuel Pool shall have a maximum fuel loading of 15.2 grams of L*ranium-235 per axial centimeter.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The conoonents identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7.1-1.

l L

Amendment No. 15 HATCH - UNIT 2 5-4