ML20097A758

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Proposed Tech Spec Changes Providing Addl Restriction on Plant Operation During Limiting Condition for Operation W/ One Recirculation Loop Out of Svc & Removing 1 H Time Period Allowed Prior to Blockage of Control Rod Withdraw
ML20097A758
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 09/06/1984
From:
GEORGIA POWER CO.
To:
Shared Package
ML20097A746 List:
References
TAC-54432, NUDOCS 8409130369
Download: ML20097A758 (6)
v • d • e


Text

{{#Wiki_filter:7. u, ATTACINENP 1 NBC DOOGT 50-321 OPERATING LICENSE DPR EIMIN I.. HA101 NUCIEAR PIANT LNIT 1 REVISION TO PRO 10 SED APRM/RBM 7ECHNICAL SPECIFICATIONS . The - proposed charges to Technical Specifications (Appendix A to Operatirg License:DPR-57) would be incorporated as follows: Remove Page - Insert Page 3.2-16a* 3.2-16a* 3.3-5* 3.3-5* 3.6-10 3.6-10 Figure 3.6-5

  • These pages sha21d be used to replace the pages of the same respective rumber..- which were enclosed with the GPC Technical Specifications charge proposal dated February 6,1984 (NED-84-030).

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g Tchle 3.2-7 (Centinued)- i f Required' 1 .[ ' Operable l L Ref. Trip. Channels No.- Condition per Trip [ (a) , Instrument Nomenclature' . System -Trip Setting ' Remarks 4 RBM Upscale 1(e)(f) a. If-Low Trip i 117/125 of fu11' scale.There are three upscale trip.' levels. Setpoint (LTSP). M-Only one is applied-over a specified operating core thermal power, range. Intermediate Trip. 1 111.2/125 of full scale All RBM trips are automatically by - 'y Setpoint (ITSP) -passed below the low power setpoint. The upscale LTSP is applied betweenc High Trip .1 107.4/125 of full scale the low power'and the-intermediate i Setpoint (HTSP) power setpoints.. The upscale ITSP is applied between the intermediate; power setpoint'and'the high. power- } setpoint. The upscale'HTSP is } applied above the high power. set-y point. io 4 Power Range Not 8' Setpoints applicable . Low Power i 30% rated core thermal' Power range setpoints control the Setpoint (LPSP) power enforcement of the appropriate up-scale trips over the proper core } Intermediate Power i 65% rated core thermal thermal power ranges. The power-b Setpoint (IPSP) power signal to the.RBM is provided by. kg, the APRM. I High Power 1 85% rated core thermal Setpoint (HPSP) power y-Bypass Time Not 1 2.0 seconds RBM bypass time delay is set low. r Delay (td2) applicable enough to assure minimum rod move-e ment while upscale trips are by-(

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l - LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.F. Operation with a-Limiting Control 4.3.F Operation with a Limiting Control Rod Pattern (for Rod Withdrawal Rod Pattern (for Rod Withdrawal Error, RWE) Error, RWE) A Limiting Rod Pattern for RWE exists During operation when a Limiting when: Control Rod Pattern for RWE exists and only one RBM channel is 1. Thermal power is below 90% operable, an instrument functional of rated and the MCPR is less test of the RBM shall be performed than 1.70, or prior to withdrawal of the control rod (s). A Limiting Rod Pattern for 2. Thermal power is 90% of rated RWE is defined by 3.3.F. or above and the MCPR is less than 1.40. During operation with a Limiting Control Rod Pattern for RWE and when core thermal power is 2 30%, either: 1. Both RBM channels shall be oper-G. Limiting the Worth of a Control Rod able, or Below 20% Rated Thermal Power 2. If only one RBM channel is oper-

1. Rod Worth Minimizer (RWM) able, control rod withdrawal shall be blocked within 24 hours, or Prior to the start of control rod withdrawal at startup, and as soon 3.

If neither RBM channel is oper-as automatic initiation of the RWM able, control rod withdrawal shall occurs during rod insertion while be blocked. shutting down, the capability of the Rod Worth Minimizer to properly G. Limiting the Worth of a Control Rod fulfill its function shall be veri-Below 20% Rated Thermal Power fled by the following checks. 1. Rod Worth Mininizar (RWM)

a. The correctness of the control rod withdrawal sequence input to Whenever the reactor is in the Start the RWM computer shall be veri-

& Hot Standby or Run Mode below 20% fled. rated thermal power, the Rod Worth Minimizer shall be operable or a

b. The RWM computer on line diag-second licensed operator shall nostic test shall be successfully verify that the operator at the performed.

reactor console is following the control rod program,

c. Proper annunciation of the selec-tion error of at least one out-of-sequence control rod in each fully inserted group shall be verified.
d. The rod block function of the RWM shall be verified by withdrawing or inserting an out-of-sequence control rod no more than to the block point.

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b -' LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 4.6.I. Jet Pm ps (Continued) e a

2. The indicated value of core flow rate varies fr m the value derived frm loop flow measurments by more than 10%.
3. The diffuser to lower plen s differential pressure reading on an individual jet pmp vary frm the mean of all jet pmp t

differential pressures by more than 10%. 3.6;J. ~ Recirculation Pmp Speeds 4.6.J. Recirculation Pmp Speeds

1. Core thermal power'shall not exceed Recirculation pmp speeds shall be 1% of rated thermal pow & without recorded at least once per day, forced recirculation.
2. Operation with a single recirculation-pmp is permitted for 24 hours unless -

the recirculation pmp is sooner made operable. With one' recirculation pump not in operation, initiate action within 15 minutes or continue action to reduce reactor power to or below the limit specified in Figure 3.6-5 within 2 hours. If the pmp cannot be made operable or the limit of Figure '3.6-5 cannot. be met within the required time, the reactor shall be in cold shutdown within 24 hours. 3.' Following one pmp operation the discharge valve of the low speed p m p may not be opened unless the speea of .the faster pm p is less than P% of its rated speed. K. Structural Integrity of Primary K. Sy uctUtal Integrity of Primary Systen Boundary M eif Exndary 'Ibe structural. integrity of the A service inspection of primar systen boundary shall be ,, i Psible cmponents listed in maintained at the level required to Ta>1e 4.6-1 will be conducted assure safe operation throughout the before initial fuel loading to life of the unit. %e reactor shall establish a preservice base for be maintained in a Cold Shutdown later inspections. ne Condition until each indiciation of a wiestructive inspections listed -defect has been investigated and 1.. Table 4.6-1 shall be performed evaluated. as specified. The reeIts obtained frm cmpliance with this specification will be evaluated after 5 years and the conclusions of this evaluation will be reviewed with the NRC. 3.6-10 ~ v

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e 1 .w ATTACWENr 2 NRC DOOTP 50-321 ) OPERATING LICENSE DPR-57 EIMIN I. HNIGI NUCIEAR PLANT LNIT 1 f; REVISION 'IO PROPOSED APRM/RBM TECHNICAL SPECIFICATIONS The following is a listing of the specific Technical Specifications revisions reglested by this subnittal and -the basis for consideration of these changes as not. involving a significant hazard as described in 10 CFR 50.92: 1) Add "With one recirculation pang not in. operation, initiate action within 15 mimtes and continue action to reduce reactor power to or below the limit specified in Figure 3.6-5 within 2 hours." and "... or the limit of Figure 3.6-5 cannot be met within the reglired time..." to Specification 3.6.J.2, and add Figure 3.6-5 as a new page. BASIS: This change would restrict plant operation to the region at or below the limit shown in Technical Specifications Figu re 3.6-5, within -2 hours after either recirculation loop is declared inoperable. That limit corresponds to a load line leading to 80% . reactor power at rated core flow. This constitutes an additional restriction not presently.in the Technical Specifications; therefore, this proposed change is consistent with Item (ii) of tre " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations". listed on page 14,870 of tre { April 6, 1983, issue of the Federal Register. 2) Add "<" to the RBM - L'ISP Trip Setting on Table 3.2-7. BASIS: This charge corrects an onunission in the 'mchnical Specifications revisions proposed by NED-84-030 (dated February 6, 1984) and otherwise has no effect -on the significant hazards evaluation for that a>bnittal. 'Iherefore this proposed change is consistent with Item (i' 'of the "Exanples of Amendments that are Considered Not Likely to -Involve Significant Hazards Considerations" listed on page 14,870 of the April 6,1983, issue of the Federal Register.

3) Remove "...within 1 hour" from Specification 3.3.F.

BASIS: This charge is within the bounds of the significant hazards evaluation enclosed.in NED-84-030 (dated February 6,1984), and has no affect on the conclusions of that evaluation. September 6, 1984}}

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