ML19247A060

Amends 50 & 47 to Licenses DPR-39 & DPR-48,respectively, Changing Tech Specs to Modify pressure-temp Operating Limits to Meet Requirements of 10CFR50

ML19247A060
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Site:	Zion  File:ZionSolutions icon.png
Issue date:	06/18/1979
From:	Schwencer A Office of Nuclear Reactor Regulation
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ML19247A056	List: ML19247A055 ML19247A060 ML19247A066 ML19247A068
References
NUDOCS 7907270193
Download: ML19247A060 (20)

Text

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_C W ASHINGTON, D. C. 20555

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COMMONWEALTH EDISCN COMPANY DOCV.ET NO. 50-295 ZION STATION UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. DPR-39 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company

( the licensee) dated February 26, 1979, as suppleme'ted May 11, 1979, 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; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commi s si on; 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 applicable reouire-ments have been satisfied.

424 238 7 9 0727 0 l eg

. 2.

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 License No. DPR-39 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Aopendices A and B, as revised throLgh Amendment No. 50, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION f/

(/$

l" r

A. Schwencer, Chief Operating Reactors branch #1 Disision of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: June 18, 1979 424 239

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COMMONWEALTi; EDIS0ti COMPANY DOCKET NC. 50-304 ZION STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE a.mendment No. 47 uicense No. DPR-48 1.

The Nuclear Regul3 tory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated February 26, 1979, as supplemented May 11, 1979,

'mplies with the standards and requirements of the Atomic _..ergy Act of 1954, as amended (the Act), and the Commissio..'s rules ard 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 ules 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 regulatiens; 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 I.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfieo.

A24 240 nesm

. 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicateo in the attachment to this license amendment and paragraph 2.C.f.2) of Facility License No. OPR-48 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 47, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/

d'htof&

A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors

Attachment:

Changes to the Technical Specifications Date of Issuance: June 18,1979 424 241

ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 50 TO FACILITY OPERATING LICENSE NO. OPR-39 AMENDMENT NO. 47 TO FACILITY OPERATING LICENSE NO. DPR-48 DOCKET N05. 50-295 AND 50-304 Revise Appenaix A as follows:

Remove Pages Insert Pages vii vii 79 79 80 80 81 81 82 82 (Intentionally Blank) 83 83 (Intentionally Blank) 84 84 85 85 86 86 87 87 90 90 91 91 92 92 93 93 94 94 (Intentionally Blank) 424 242

LIST OF FIGURES (Continued)

Page F igu re 84 3.3.2-1 Reactor Coolant System Heatup Limitations 85 3.3.2-2 Reactor Coolant System Cooldown Limitations 3.3.2-3 Effect of Fluence and Copper Content on Shift af 86 0

RT for Reactor Vessel Steels Exposed to $50 F Temperature 3.3.2-4 Fluence at 1/4T and 2/4T as a Function of Full Power 87 l

Service Years 329 6.1.1 Commonwealth Edison Corporate Organization 330 6.1.2 Station Organization chart 331 6.1.3 Zion Shift Manning Chart b

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V PN) 4 U

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LIF.ITII;G CC::DITION FOR CPERATION SURVEILLANCE REQUIREMENT

3. 3 2.

Pressurization and Systen Integrity 4.3 2.

Pressurization and System Integrity A.

Heatap and Cooldown A.

Not Applicable The Reactor Coolant System temperature and pressure (with the exception of the pressurizer) shall be limited in accordance with the limit lines shown in Figures 3.3.2-1 and 3.3.2-2 during heatup, cooldown and inservice leak and hydrostatic testina.

l.

Allowable combinations of pressure and temperature for specified temperature change rates are below and of the right of the limit lines shown.

Limit lines for cooldown rates between those presented may be obtained by interpolation.

2.

Figures 3.3.2-1 and 3.3.2-2 define limits to ass ure prevention of non-ductile failure only.

For normal operation other inherent plant characteristics, e.g.,

43, pump heat addition and py pressurizer heater capacity 43, may limit the heatup and cooldown rates that can be ps) achieveJ over certain pressure-4s-tempe ratu re ranges.

4:=

3.

The Reactor Coolant System shall be limited to a maximum temperature change of 100F/hr during inservice 79

O O

O LD'.ITIt.'G CONDITICN FOR OPERATION SURVEILLA!CE REQUIREMENT 3.3.2.

A3. (Continued) leak and hydrostatic testing ope)ations above the heatup and ccoldown limit curves.

B.

The limit lines shown in Figures 3.3.2-1 and ;3.3.2-2 shall be recalculated periodically as requivaa-hased on results from the material surveillance program.

C.

The secondary side of the steam generator must be pressurized above 200 psig if the temperature 0

of the vessel is below 70 F.

D.

The pressurizer heatup rate shall not 0

exceed 100 F/hr and the pressurizer 0

cooldown rate not exceed 200 F/hr.

The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is greater than 3200F.

E.

Hydrostatic Testing 1.

System inservice leak and hydrotests shall be performed in accordance with the require-ments of ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, up to and including Summer 1975 Addendum.

45.

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1. I 80

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O LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMElIT 3.3.2.

A3. (Continued) leak ar.d hydrostatic testing operations above the heatup and cooldown limit curves.

B.

The limit lines shown in Figures 3.3.2-1 and23.3.2-2 shall be recalculated periodically as required, based on results f rom the material surveillance program.

C.

The secondary side of the steam generator must be pressurized above 200 psig if the temperature 0

of the vessel is below 70 F.

D.

The pressurizer heatup rate shall not 0

exceed 100 F/hr and the pressurizer 0

cooldown rate not exceed 200 F/hr.

The spray shall not be used if the temperature difference between the pressurizer and the spray fluid is 0

greater than 320 F.

E.

Hydrostatic Testing 1.

System inservice leak and hydrotests shall be performed in accordance with the require-ments of ASME Boiler and Pressure Vessel Code,Section XI, 1974 Edition, up to and including Summer 1975 Addendum.

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LI:~.ITIt:0 CCNDITICN FOR CPERATION SURVEILLANCE REQUIRE:~.ElC 3.3.2 4.3.2 l

F.

Safety Injection Actuation F.

Not Applicable 1.

If safety injection should occur when a reactor is in the hot shut-down condition or above, the reactor shall remain in the hot shutdown

~

condition until the status of the reactor coolant system integrity is determined.

2.

If the inspection and review (Sec.

6.1. G. 2. a ( 7 ) and Sec.

6. 3) of the reactor coolant system integrity determines that:

a.

The injection did not affect reactor coolant system integrity the plant may proceed to power operation.

b.

The injection did affect reactor coolant system integrity, the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 3.

The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and an analysis of tha incident shall be submitted to a3.

ps) the NRC within 90 days.

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Bases 3.3.2 Fracture Toughness Properties program, when evaluated according to ASTM E185, indicate that they are 3.3.4 The fracture toughness properties of the inappropriate.

At this time, the ferritic materials in a reactor coolant heatup and cooldown curves must be re-pressure boundary are determined in calculated.

accordance with Section III of the AS ME Boiler and Pressure Vessel Code, The length of the first full power service l

1974 Edition.

(1).

Heatup and cool-period has been chosen such that the limiting down limit curves are calculated using the RTNDT at the 1/4 T vessel location includes most limiting value of RT determined a radiation induced ARTNDT on the order of NDY as follows:

100-1500F.

The assumption of a radiation induced shift of this magnitude assures that 1.

De te rmine the highest RT of the all other components in the primary pressure N DT ma te ri a l in the core region of a boundary will be operated conservatively, reactor vessel using original in accordance with code recommendation.

values from Table 3.3.2-1 and estimating the radiation induced d RT using Figure 3.3.2-3 Heatup and Cooldown Limit Curves

( Re fe rkkce 6 & 7 ).

N Fast neutron (E > l Mev) fluence Allowable pressure-temperature relationships at the 1/4 T and 3/4 T vessel for various heatup and cooldown rates are locations are given as a calculated using methods derived from Non function of full power service Mandatory Appendix G2000 in Section III of life in Figure 3.3.2-4.

the ASME Boiler and Pressure Vessel Code; and discussed in det! il in Reference (2).

2.

Examine the data for all other ferritic The soproach specified that the allowable naterials in a reactor coolant pressure total stress intensity factor (Ky) at any boundary to assure that no other time during heatup or cooldown cannot be component will be limiting.

greater than that shown on the K curve yp (Reference 1) for the metal temperature at 3.

Initially, the effect of radiation that time.

Furthermore the approach applies on the RTNDT of a reactor vessel explicit safety factors of 2.0 and 1.25* on 45 core region material is estimated stress intensity f a ctors induced by pressure Ib}

using the curves shown in Figure and thermal gradients, respectively.

Thus, 4"

3.3.2-3.

Thet '

shown for the the governing equation for the heatup-cooldown 4

first eight e COTlve full power analysis is:

p[)

years is fat d into the heatup and cocidown

..rves provided.

ty, Values ofARTNDT determined in

• The 1. 25 safety f actor on K represents It 43 this manner may be used until the additional conservatism above Code results f rom the material surveillance requirements 90

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The cooldown analysis proceeds in the same Heatup and cooldown limit curves shown fashion as that for heatup, with the excep-are the results of the above analysis.

tion that the controlling location is The most limiting material properties for alwaya at 1/4T.

The thermal gradients both reactor vessels were used in a induced during cooldown tend to produce single analysis, therefore, the curves tensile stresses at the 1/4T location and apply conservatively to both units.

compressive stresses at the 3/4T position.

Thus, the ID flaw is clearly the worst case.

As in the case of heatup, allowable pressure Pressurizer Limits temperature relations are generated for both steady state and finite cooldown zate Although the pressurizer operates at situations.

Composite Ibnit curves are then tempe rature ranges abcae those for which constructed for each cooldown rate of interest.

there is reason for concern about l

brittle fracture, operating limits are The use of the composite curve in the cool-provided to assure compatability of down analysis is necessary because system operation with the faJue analysis control is based on a measurement of reactor performed in accordance with Code require-coolant temperature, whereas the limiting ments.

pressure is calculated using the material temperature at the tip of the assumed reference flaw.

During cooldown, the 1/4T vessel location is at a higher temperature than the fluid adjacent to the vessel ID.

This condition is, of course, not true for the steady-state situation.

If follows that the dT induced during cooldown reeults in a calculated higher Lilowable K for finite cooldown yg rates than for steady state under certain conditions.

Apggetails of these calculations are provided

.ed n Re f erence (2).

92 r\\)

Ln CN

Hydrostatic Testing Limit Curve Allowable pressure-temperature relationships 3.

ASME Boiler and Pressure Vessel for leak and hydrostatic testing are als Code,Section III, N-331 calculated usina methods derived from Non-Mandatory Appendix G2000 in Section III of 4.

ASME Boiler and Pressure Vessel the ASME Boiler and Pressure Vessel Code.

Code Section III, N-415 The approach specified is the same as described for heatup and cooldown limits 5.

FSAR, Chapter 4.3 except that the safety factor on KI is m

reduced to 1. 5 and there are no significant 6.

WCAP - 87_

" AS ME III, Appendix thermal transients or gradients.

Thus G Analysis of the Commonwealth the governing equation for the leak and Edison Company Zion Unit 1 Peactor hydrostatic testing analysis is:

Vessel" l

1.5 KI K

7 W CAP - 8 7 2 7, " AS ME III, Appendix G m

IR Analysis of the Commonwealth Edison 7 Reactor Vesse?".

Inadvertent Safety Injection Company Zion Unit In the event of an inadvertent safety injection actuation the affected reactor will trip immediately, placing the reactor in the hot shutdown condition.

After 90 seconds safety injection may be reset ord injection terminated a.=

required.

inspection of the primary system while An at hot shutdown will prevent possible degradations in tne primary system for undergoing further immediate thermal shock imposed during a cooldown.

If degradations in the primary system are discovered an orderly controlled cooldown wil! be planned to minimize the ef fects of thermal shock on these cagradations on the affected unit.

'D' Re fe rences :

N

1. • • l.

ASME Boiler and Pressure vessel Code,Section III N

ty) 2.

WCAP - 7924, " Basis for heatup and Cooldown Limit Curves", July 1972

's) 93

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H A24 258