ML20058F560
| ML20058F560 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/13/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058F565 | List: |
| References | |
| NUDOCS 8207300565 | |
| Download: ML20058F560 (6) | |
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NUCLEAR REGULATORY COMMISSION.
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BALTIM0RE GAS AND ELECTRIC COMPANY n
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DOCKET NO. 50-317 4
CALVERT CLIFFS NUCLEAR POWER PLANT UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. DPR-53 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Company (the licensee) dated June 30, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Com-mission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 Comission's regula-tions; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of.
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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.
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-53, is hereby amended to read as follows:
(2) Technical Specifications q
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 72, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION q
Robert A. C1' ark, Chief
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Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: July 13, 1982 y
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ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. DPR-5.7 DOCKET.NO. 50-317 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area'of change.
The corresponding overleaf pages are also provided to main-tain document completeness.
Remove Insert 3/4 2-14 3/4 2-14 3/4 2-15 3/4 3-21 3/4 3-21 3/4 7-9 3/4 7-9 N
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r POWER DISTRIBUTION LIMITS DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB related parameters shall be maintained within L
the limits shown on Table 3.2-1:
a.
Cold Leg Temperature b.
Pressurizer Pressure c.
Reactor Coolant System Total Flow Rate d.
AXIAL SHAPE INDEX, Core Power APPLICABILITY: MODE 1.
ACTION:
With any of the above parameters exceeding its limit, restore the parameter to within its 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 5% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE REQUIREMENTS c
4. 2. 5.1 Each of the parameters of Table 3.2-1 shall be verified to be within their limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4.2.5.2 The Reactor Coolant System total flow rate shall be determined to be within its limit by measurement at least once per 18 months.
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LIMITS
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Parameter Operating Operating Operating-Same Loop Operating-Opposite Loop g
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Cold Leg Temperature
< 548 F
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> 2225 psia
f Total Flow Rate
> 370,000 gpm E
AXIAL SilAPE INDEX R
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- Limit not applicable during either a THERMAL POWER ramp increase in excess of 5% of RATED TilERMAL POWER
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per minute or a THERMAL POWER s,tep increase of greater than 10% of RATED THERMAL POWER.
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four reactor coolant pumps operating.
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OPERABLE, or within the limits of FIGURE 3.2-4 for CEA insertions specified by FIGURE 3.1-2.
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'l TABLE 3.3-5 (Continued) l ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 1
6.
Steam Generator Pressure-Low
.l a.
Main Steam-Isolation 1 6.9-b.
Feedwater Isolation 1 80 L
7.
Refueling Water Tank-Low a.
Containment Sump Recirculation 1 80 8.
Reactor Trio a.
Feedwater Flow Reduction to 5%
1 20 l
9.
Loss of Power 4
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4.16 kv Emergency Bus
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Undervoltage (Loss of j
Voltage) b.
4.16 kv Emergency Bus 1 8.4 q
Undervoltage (Degraded i
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Voltage)
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10.
Steam Generator Level - Low a.
Auxiliary Feedwater System 1 360*/360**(2) j l
J TABLE NOTATION 4
Diesel generator starting and sequence loading delays included.
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Diesel generator starting and sequence loading delays not included.
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Offsite power available.
- Response time measured from the incidence of the undervoltage condition to the diesel generator start signal.
(1) Header fill time not included.
(2)
Includes time delay of 3 to 5 minutes.
CALVERT CLIFFS - UNIT 1 Amendment No. 44. $A, 7 6 72*
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TABLE 4.3-2 h%
ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTAION SURVEILLANCE REQUIREMENTS Mg j{
x x CHANNEL MODES IN WHICH C[
c, CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE I
c FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED
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SAFETY INJECTION (SIAS) e I
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Manual (Trip Buttons)
N.A.
N.A.
R N.A.
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b.
Containment Pressure - liigh S
R M
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c.
Pressurizer Pressure - Low S
R M
1, 2, 3 d.
Automatic Actuation Logic H.A.
N.A.
M(1)(3) 1, 2, 3 m
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CONTAINMENT SPRAY (CSAS) i a.
Manual (Trip Buttons)
N.A.
N.A.
R N.A.
g b.
Contair..ent Pressure --
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R M
1,2,3 h
c.
Automatic Actuation Logic N.A.
N.A.
M(1) 1, 2, 3
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CONTAINMENT ISOLATION (CIS) #
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Manual CIS (Trip Buttons)
N.A.
N.A.
R N.A.
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Containment Pressure - High S
R M
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c.
Automatic Actuation Logic N.A.
N.A.
M(1)(4) 1, 2, 3 a
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MAIN STEAM LINE ISOLATION (SGIS) a.
Manual SGIS (MSIV Hand FF Switches and Feed Head 8@
Isolation Hand Switches)
N.A.
N.A.
R N.A.
b.
Steam Generator Pressure - Low S R
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Automatic Actuation Logic N.A.
N.A.
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- Containment isolation of non-essential penetrations is also initiated by SIAS -(functional units wm
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PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES
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LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY: MODES 1, 2 and 3.
ACTION:
MODE 1 With one main steam line isolation valve inoperable, POWER OPERATION may continue provided the inoperable j
valve is either restored to OPERABLE status or closed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
MODES 2 With one main steam line isolation valve inoperable, sub-and 3 sequent operation in MODES 1, 2 or 3 may proceed provided:
O' a.
The isolation valve is maintained closed.
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The provisions of Specification 3.0.4 are not applicable.
Otherwise, be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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SURVEILLANCE REQUIREMENTS o
4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 3.6 seconds when tested l
N pursuant to Sp.ecification 4.0.5.
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CALVERT CLIFFS-UNIT 1 3/4 7-9 Anendment No. 471 72 J
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CALVERT CLIFFS - UNIT 1 3/4 7-10 Amendment No. H, 59 i
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