ML20216J493
| ML20216J493 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/10/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Public Service Electric & Gas Co, Philadelphia Electric Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20216J498 | List: |
| References | |
| DPR-75-A-183 NUDOCS 9709170337 | |
| Download: ML20216J493 (9) | |
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f-P; NUCLEAR REGULATORY COMMISSION k
WASHINGTON, D.C. seteHoot 1,
PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50 311 SALEM NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 License No. DPR 75 1.
The Nuclear Regulatory Comission (the Comission or the NRC) has found that:
A.
The application for amendment filed by the Public Service Electric &
Gas Company, Philade13hia Electric Company Delmarva Power and Light Company and Atlantic Cit Electric Company (the licensees) dated August 19, 1997, as supp emented by letter dated August 20, 1997, com lies with the standards and requirements of the Atomic Energy Act of 954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the arovisions of the Act, and the rules and regulations of the Comission:
C.
There is reasonable assurance: (1) 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 set forth in 10 CFR Chapter I:
D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.
2, Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR 75 is hereby amended to read as follows:
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j 2-(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in A)pendices A and B, as revised through Amendment No. 183, are here)y incorporated in the license. The licensee shall o the Technical Specifications. perate the facility in accordance with 3.
This license amendment is effective as of its date of issuance.-to be implemented within 7 days.
F0 THE NUCLEAR REG LATORY COMMISSION L
opnF.Stolz,Direc roject Directorate
-2 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical r
Specifications Date of issuance: September 10, 1997 a
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ATTACHMENT TO LICENSE AMENDMENT NO. 183 FACILITY OPERATING LICENSE NO. DPR 75 DOCKET NO. 50 311 Revise Appendix A as follows:
Remove Paoes Insert Paaes 3/4 1 13 3/4 1-13 3/4 1-14 3/4 1-14 3/4 1 16 3/4 1-16 I
3/4 1-16a 3/4 1 16a B 3/4 1 4 8 3/4 1 4 B 3/4 2 4 8 3/4 2 4 i
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l 7I' ACTIVITY OONTROL SYSTEMS hl. 3 MDVhEE CONTROL ASEDfBLIES GROUP IfEIGHT LIMITING CONDITION FOR OPERATION 3.1.3.1 All full length (ahutdown and control) rods, shall be OPERABLE and positioned within 1 18 steps (indicated position) when reactor power is s 85%
RATE 3 THER)V1 POWER, or 1 12 steps (indicated position) when reactor power is
> Bbn RATED THERMAL POWER, of their group step counter demand position within one hour after rod motion.
APPLICABILITY: MODES 1* and 2*
ACTION :
a.
With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SNUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With more than one full length rod inoperable or mis-aligned from the group step counter demand position by more than i 18 steps (indicated position) at s 85% RATED THERMAL POWER or 1 12 steps (indicated position) at > 85% RATED TIIERMAL POWER. be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
Witti one full length rod inoperable due to causes other than addressed by ACTION a, above, or mis aligned from its group step counter demand position by more than t 18 steps (indicated position) at s 85% RATED THERMAL POWER or 1 12 steps (indicated position) at > 85% RATED THERMAL POWER, POWER OPERATION may continue provided that within one hour either 1.
The rod is restored to OPERABLE status within the above alignment requirements, or 2.
The remainder of the rods in the bank with the inoperable rod are aligned to within 1 18 steps (indicated position) at s 85% RATED THERMAL POWER or t 12 steps (indicated position) at >S5% RATED THERMAL POWER, of the inoperable rod while maintaining the rod sequence and insertion limits of Figures 3.1 1 and 3.1 2; the THERMAL POWER level shall be restricted pursuant to specification 3.1.3.5 during subsequent operation, or 3.
The rod is declared inoperable and the SHVfDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
- See Special Test Exceptions 3.10.2 and 3.10.3.
SALEM UNIT 2 3/4 1-13 Amc"dment No.183 l
l a)
A reevaluation of each accident analysis of Table 3.1 1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions, b)
The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
c)
A power distribution map "is obtained f rom the movable incore detectors and Fn(Z) and F 4H are verified to be within their limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
d)
The THERMAL POWER level is reduced to less than or equal to 75% of RATED THEPFAL POWER within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the high neutron flux trip setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.
THERMAL POWER shall be maintained less than or equal to 75% of RATED THERMAL POWER until compliance with ACTIONS 3.1.3.1.c.3.a and 3.1.3.1.c.3.c above are demonstrated.
SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each full length rod shall be determined to be within the limits established in the limiting condition for operation at least I once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (allowing for one hour thermal soak after rod motion) except during time intervals when the Rod Position Deviation Monitor is inoperable, then verify the group positions at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each full length rod not fully inserted in the core shall be determined to be OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.
1 SALEM - UNIT 2 3/4 1-14 Amendment No.183
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REAETIVITY CONTROL SYSTEMS POEITION TMDIcATION SYSTEMB - OPERATING l
LIMITING CONDITION FOR OPERATION j
3.1.3.2.1 The shutdown and control rod position indication systems shall be OPERAsLE and capable of determining the actual and demanded rod positions as follows:
s.
Analog rod position indicators, within one hour after rod motion (allowance for thermal soak)
All shutdown aank.: 1 18 steps at s95% reactor power or if reactor power is > 85% RATED THERMAL F0WER 1 12 steps of the group de and counters for withdrawal ranges of 0 30 steps and 200 228 steps, control mank Al 1 18 steps at s054 reactor power or if reactor power is >
854 RATED THERMAL POWER t 12 steps of the group demand counters for withdrawal ranges of 0 30 steps-and 200 228 steps.
control Rank B: 1 18 steps at sO5% reactor power or if reactor power is >
85% RATED THERMAL POWER 1 32 steps of the group demand counters for withdrawal ranges of 0 30 steps and 160 228 steps.
control manks c and De i le steps at s95% reactor power or if reactor power is > 85% RATED THERMAL POWER 1 12 steps of the group demand counters for withdrawal range of 0 228 steps.
b.
Group demand counters;
- 2 steps of the pulsed output of the Slave cycler circuit over the withdrawal range of 0 228 steps.
APPLICABILITY: MODES 1 and 2.
ACTION:
With a maximum of one analog rod position indicator per bank a.
inoperable either:
- 1. Determine the position of the non-indicating rod (s) indirectly by the movable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and within one hour after any motion of the non indicating rod which exceeds 24 steps in one direction since the last detwrmination of the rod's position, or
- 2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, b.
With two or more analog rod position indicators per bank inoperable, within one hour restore the inoperable rod position indicator (s) to OPERABLE status or be in NOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
A maximum of one rod position indicator per bank may remain inoperable following the hour, with Action (a) above being applicable from the original entry time-into the LCo.
SALEM ' UNIT 2 3/4 1 Amendment No.183 l
i With a maximum of one group demand position indicator per bank c.
inoperable either 1.
Verify that all analog rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 10 steps when reactor power is s 85% RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL POWER, 12 steps of each other at 3 east once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.
Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.1.3.2.1.1 Each analog rod position indicator shall be determined to be OPERABLE by verifying that the demand position indication system and the rod position indication system agree within 18 steps when reactor power is s 85%
RATED THERMAL POWER or if reactor power is > 85% RATED THERMAL p0WER, 12 steps (allowing for one hour thermal soak after rod motfon) at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when the Rod position Deviation Monitor is inoperable, then compare the demand position indication system and the rod position indication system at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.2.1.2 Each of the above required rod position indicator (s) shall be determined to be OPERABLE by performance of a CHANNEL calibration at least once per 18 months.
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SALEM - UNIT 2 3/4 1 16a Amendment No.183 l~
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REACTIVITY CONTROL SYSTEMS BASES The boron capability required below 200'F is suf ficient to provide a SHUTDOWN MARGIN of 14 delta k/k after xenon decay and cooldown from 200'F to 140'F.
This condition requires either 2,600 gallons of 6,560 ppm borated water from the beric acid storage tanks or 7,100 gallons of 2,300 ppm borated water from the refueling water storage tank.
The 37,000 gallons limit in the refueling water storage tank for Modes 5 and 6 is based upon 21,210 gallons that is undetectable due to lower tap location, 8,550 gallons for instrument error, 7,100 gallons required for shutdown margin, and an additional 140 gallons due to rounding up.
The limits on contained water volume and boron concentration of the RWST also ensure a~pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.
This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.
The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity contro2 while in MODE 6.
3/4.1.3 MOVABLE CONTROL ASSEMPLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effects of rod mis-alignment on associated accident analyses. OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits. OPERABLE condition for the analog rod position indicaters is defined as being capable thebankdemandpositionforarangeofpositions.FortheShutdownBanks,andl of indicating rod position to within the allowed rod misalignment relative to Control Bank A this range is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 200 and 228 steps withdrawn inclusive. This. permits the operator to verify that the control rodn in these banks are either fully withdrawn or fully inserted, the normal operating modes for these banks.
Knowledge of these banks positions in these ranges satisfies all accident analysis assumptions concerning their position. The range for control Bank B is defined as the group demand counter indicated position between 0 and 30 steps withdrawn inclusive, and between 160 and 228 steps withdrawn inclusive.
For Control Banks C and D the range is defined as the group demand counter indicated position between 0 and 228 steps withdrawn. Compsrison of the group denand counters to the bank insertion limits with verification of rod position with the analog rod position indicatots (after thermal soak after rei motion) is sufficient verification that the control rods are above the insertion limits. The full out position will be specifically established for each cycle by the Reload Safety Ann ysis for that cycle. This position will be within the band established by " FULL WITHDRAWN" and will be administratively controlled. This band is allowable to minimize RCCA wear, pursuant t0 Informa*. ion Notice 87-19.
SALEM - Jr i1 B 3/4 1-4 Amendment No.lO3 l
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POWER DISTRIBUTION LIMITS RASES 3 /4.2 7 and 3 /4.2. 3 HEAT FLUX AND NUCLEAR ENTHALPY HOT CHANNEL AND RADIAL PEAXING FACTORS - Fn(Z) AND F"an The limits on heat flux and nuclear enthalpy hot channel factors and RCS flow rate ensure that 1) the design limits on peak local power density and minimum DNBR are not exceeded and 2) in the event of a LOCA the peak fuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit.
Each of these hot channel factors are measurable but will normally only be determined periodically as rpecified in Specifications 4.2.2 and 4.2.3.
This periodic surveillance is sufficient to insure that the limits are maintained provided:
a.
Control rod in a single group move together with no individual rod insertion differing from the group demand position by more than the l allowed rod misalignment.
b.
Control rod groups are sequenced with overlapping groups as described in Specification 3.1.3.5.
c.
The centrol rod insertion limits of Specifications 3.1.3.4 and 3.1.3.5 are naintained, d.
The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits.
The relaxat:on in F",n as a function of THERMAL POWER allows changes in the radial power shape for all permissible rod insertion limits.
F",n will be maintained within its limits prcvided conditions a through d above, are maintained.
When an Fg measurement is taken, both experimental error and manufacturing tolerance must be allowed for. Five percent is the appropriate allowance for a full core map taken with the incore detector flux mapping system and 3% is the appropriate allowance for manufacturing tolerance.
When F",n is measured, experimental error must be allowed for and 4% is the appropriate allowance for a full core map tan with the incore detection e
system. The specified limit for F",n also contains an 8% allowance for uncertainties which rean that normal operation will result in F"an s1.55/1.08 The 8% allowance is based on the following considerations:
l, SALEM - UNIT 2 B 3/4 2-4 Amendment No.163 l
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