ML19343D238
| ML19343D238 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 04/20/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19343D233 | List: |
| References | |
| NUDOCS 8105040025 | |
| Download: ML19343D238 (6) | |
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/sV, ORDER FOR MODIFICATION OF LICENSE (EVENT V)
PALISADESPLANY DOCKET NO. 50-255 Delete "(where appropriate and insert the fellowing pages in the Technical Specifications:
Pages 3-30 3-30a*
4-17 4-18
- 4-19 l
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~~There tre no chcnges to the provisions contcined on this pcge. it is j
l ir.cluded for pt;cinction purposes only.
!81050400 2
3.3 EMERGENCY CORE COOLING SYSTEM (Contd) g.
A maximum.of cne high-pressure safety injection pump shall be OPERABLE whenever the temperature ' f one or more of the,PCS cold o
legs is < 250*F.
3.3.3 Prior tio returning to the Power Operation Condition after every time the plant has been placed in the Refueling Shutdown l
Condition, or the Cold Shutdown Condition for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and testing of Specification 4.3.h has not been accom-lished in the previous 9 months, or prior to returning the check valves in Table 4.3.1 to service after maintenance, r,epair or replacement, the following condi+,fons shall be met:
All pressure isolation valves listed in Table 4.3.l'shall be a.
functional as a pressure isolation device, except as speci-fied in b.
Valve leakage shall not exceed the amounts indicated.
b.
In the event that integrity of any pressure isolation valve specified in Table 4.3.l cannot be demonstrated, at least e
two valves in each high'~ pressure line having a non-functional valve must be in and remain in, the mode corresponding to theisolatedcond,itice..,(I) c.
If Specification a. and b. cannot be met, an orderly shutdown shall be initiated and the reactor shall be in hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and cold shutdown within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 NRC Order dated 3-30 Amendment No. Ef, April 20,1981 IMotor-operated valves shall be placed in the closed position and
- mte r supplies deenergized.
Basis The normal procedure for starting the reactor is, first, to beat the primary coolant to near operating temperature by running the primary The reactor is then made critical by withdrawing coolant pumps.
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With control rods and diluting boron in the primary coolant.
this mode of start-up, the energy stored in the primary coolant dur-the approach to criticality is substantir.lly equal to that during in6 power operation and, therefore, all engineered safety features and During auxiliary cooling systems are required to be fulls operable.
low-temperature physics tests, there is a negligib1d amount of stored energy in the primary coolant; therefore, an accident comparable in f
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3-30a l
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in:paction techniquac thnt h va bacn prcv:n prceticci, and tha conclusions of the evaluation shall be used as appropricto to update the inspection program.
f.
Surveillance of the regenerative heat exchanger and primary coolant pump flywheels shall be performed as indicated in Table 4.3.2.
A surveillance program to monitor radiation induced changes in g.
the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR.
The specimen removal schedule shall be as indicated in Table 4.3.3.
h.
Periodic leakage testing (a), (b) on each check valve' listed in Table 4.3.1 shall be accomplished prior to returning to the Power Operation Condition af ter every time the plant has been placed in the Refueling Shutdown Condition, or the Cold Shutdown Condition for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if such testing has not been accomplished within the previous 9 months, and prior to returning the check valves to service after maintenance, repair or replace-ment work is performed on the valves.
1.
Whenever integrity of a pressure isolation valve listed in Table 4.3.1 cannot be demonstratedmand credit is being taken for
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compliance with Specification 3.3.3.b., the integrity of the j
remaining check valve in each high pr' essure line having a leaking valve shall be determined and recorded daily and the position of the other closed valve located in that high pressure line shall be recorded daily.
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HRC Order dated 4-17 Amendment No.,53, April 20,1981
- o satirfy ALARA requirements. leakage may be measured indirectly (as from the performance of pressure indicaters) if supported bv cerputatient rM inr, that the rcthed ir carct'e cf vtrenrtrntir-
-1a cer-11nece eith the lenkage criterir.
( beduced prccrure tusting is cceeptable irec-f 'etncte 5 te T:cic 1
4.3.1).
':ininur t e s t differential pressurc e :.11 nc-b thcn 150 p-id.
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4.
II. SIS The inspection pregram specified places major e=phasis en the areas cf highest stress concentraticn as deter =ined by general design evaluation
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and experience with similar systems.
In addition, that pertien of the reacter vessel shell velds which vill be subjected to a fast neu ron dose sufficient to, change ductility properties vill be inspected.
The inspec-tions vill rely pri=arily en ultrasonic methods utilicing up-to-date ana-ly:ing equip =ent and trained personnel.
Preoperational inspectiens vill establish base conditiens by deter =ining indicatiens that night occur frc gecmetrical or metallurgical sources and from discontinuities in veld:ents or plates which =ight cause undue cencern on a postservice inspection. To the extent applicable, based upon the existing design and construction of the plant, the require:ents. of Section XI of the Code shall be co: plied with.
Significant exceptions are detailed in the recuests for relief which have received NEC approval and are contained in the Class 1, Class 2 and class 3 Long-Term Inspection Plans.
REACTOR VESSEL SURVIILLtd;CE SPECIJENS Table k.3.3 is censistent with the surveillance program as presented in the FSAR.
hcvever, the withdrawal. schedule has been modified to re-flect the slign:1y different vall fiuence values resulting frem removal
- f the ther:cl snield.
EEFERCCES
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FSAR, Secti:n '.5.6.
(2) FSAR, Secticn
.5.3 i
3 4-18 Amendment No. 53 P003 gggy
m TABLE 4.3.1 PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES.
System Valve No.
Maximum ("
Allouable Leakage High Pressure Safety Injection Loop 1A, Cold Leg 3101 5.0 gpm 3104
'. 0 gpm Loop 1B, Cold Leg 3116 5.0 gpm 3119 5.0 gpm Loop 2A, Cold Leg 3131 5.0 gpm 3134 5.0 gpm Loop 2B, Cold Leg 3146 5.0 gpm 3149 5.0 gpm Low Pressure Safety Injection Loop 1A, Cold Leg 3103 5.0 gpm Loop 1B, Cold Leg 3118 5.0 gpm 313'3 5.0 gpm Loop 2A, Cold Leg Loop 2B, Cold Leg 3148 5.0 gpm Footnote:
(8)1.
Leakage rates less than or equal to 1.0 gpm are considered acceptable.
2.
Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
3.
Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previcus test by an amount
- Sat reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
4.
Leakage rates g. 6et
- ban 5.0 gpm are considered unacceptable.
5.
Measured leakage rates must be adjusted for test pressures less than the maximun potential pressure differential across the valve by assuming leakage to be directly proport ional to the pressure differential to the one-half power.
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NRC Order dated 4 19 Amendment flo. 52',
April 20,1981 l