ML20203L551
| ML20203L551 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/15/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20203L554 | List: |
| References | |
| NUDOCS 8608280025 | |
| Download: ML20203L551 (12) | |
Text
'*~
,0 s ts ouq'o, UNITED STATES
['%
I '{
NUCLEAR REGULATORY COMMISSION
- 4
~p WASHINGTON, D. C. 20555
\\....*/
e t
/
COWONWEALTH EDISnN COMPANY AND IndA-ILLINDIS GAS /FD ELECTRIC COMPANY DOCKET NO. 50-254 Ol'An CITIES MUCLEAR POWFR STATION, llNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 96 License No. DPR-2n 1.
The Nuclear Reculatory Commission (the Commission) has found that:
A.
The apolication for amendment by Cc,mnonwealth Edison Company (the licensee) dated November 1, 1982, complies with the standards and reouirements of the Atomic Enerov Act of 1954, as amended (the Act) and the Commission's rules and reculations set forth in 10 CFR Chapter I; R.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and reculations of the Commission; C.
There is reasonable assurance (i) that the activities authorized hv this amendment can be conducted without endannerino the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's reculations; D.
The issuance of this amendment will not be inimical to the commca 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 requirements have been satisfied.
2.
Accordinoly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Doerating License No. DPR-29 is hereby amended to read as follows:
8608280025 860815 DR ADOCK 0500 4
^,
-?-
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throuch Amendment No. 96, are hereby incorporated in the j
license. The licensee shall operate the facility in accordance with the Technical Specifications.
?.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION AD M
n A. Zwolinski, Director
( Division of BWR Licensing nWR Project Directorate f'l
Attachment:
Channes to the Technical Specifications Date of Issuance: August 15, 1986 f
~
ATTACFMENT TO LICENSE AMENDMENT NO. 96 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removino the pages 1
identified below and insertino the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3.7/4.7-6 3.7/4.7-6 3.7/4.7-6a 3.7/4.7-6a 3.7/4.'-13 3.7/4.7-13
/
+5 TT
QUAD-CITIES DPR-29 points along the seal surface
- 2) Vacuum breaker P sition in-of the disk.
dication and alarm systems
- 3) The position alarm system shall be calibrated and func-will annunciate in the control tionally tested.
1.
room if the valve opening
- 3) At least 25% of the vacuum exceeds the equivalent of breakers shall be inspected I/16 inch at all points along such that all vacuum breakers the seal surface of the disk.
All h c been inspected fol-
- b. Any pressure suppression cham-lowing every fourth refueling ber-drywell vacuum breaker may outage. If deficiencies are be non fully closed as indicated by found, all vacuum breakers the position indication and alarm shall be inspected and defi-systems provided that drywell to ciencies corrected.
suppression chamber differential
-)
A drywell to suppression 4
pressure decay rate is demon-
&&M shll de strated to be not greater than 25%
onstrate that with initial dif-of the differential pressure decay
- ,3
,7 rate for all vacuum breakers open than 1.0 psi the diferential the equivalent of 1/16 inch at all pressure decay rate does not points along the seal surface of the exceed the rate which would disk.
occur through a 1 inch orifice Reactor operation may continue without the addition of air or c.
provided that no more than one nitrogen.
quarter of the number of pressure suppression chamber drywell vac-uum breakers are determined to be inoperable provided that they are secu ed or known to be in the closed position.
- d. If failure occurs in one of the two-position alarm systems for one or more vacuum breakers, reactor operation may continue provided that a differential pressur: decay rate test is initiated immediately and performed every 15 days thereafter until the failure is cor-rected. The test shall meet the re-quirements of Specification 3.7.A.4.b.
- 5. Oxygen Concentration
- 5. Oxygen Concentration After completion of the startup The primary containment oxygen con-a.
test program and demonstration centration shall be measured and re-of plant electrical output, the pri-corded on a weekly basis.
mary containment atmosphere shall be reduced to less than 4%
oxygen by volume with rltrogen gas during reactor power operation with reactor coolant pressure above 90 psig, 3.7/4.7-6 Amendment No.96
w- - -. - -.
y
.--_ -.__., ~
v
--9--
=--.= --
- f. -
QUAD-CITIES DPR-29 except as specified in Specification 3.7.A.5.b.
b.
Within the 24-hour period subse-
/
quent to placing the reactor in the Run mode following a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4% by volume, and main-tained in this condition.
Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
- i. Containment Systems 6.
Containment Systems
.Drywell-Suppression Chamber Drywell-Suppression Chamber Differential Pressure Differential Pressure a.
The pressure differ-a.
Differential pressure between the drywell and ential between the suppression chamber shall drywell and suppression be maintained at equal to chamber shall be recorded at least once each shift.
or greater than 1.20 psid except as specified in (1), (2), and (3) below:
(1) This differential shall be established within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to i
placing the reactor sede switch into the RUN mode during a startup and rey be relaxed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reactor shutdown when the provisions of 3.7.A.5(b) apply.
3.7/4.7-6a Amendment No. 49, 96
@AD-CITIES DPR-29 hydrogen, if it is present in suf ficient quantities to result in ancessivaly ropid recombination, could result in a loss of contaiment integrity.
j The 4% oxygen concentration by volume minimites the possibility of hydrogen Signifigantquanitiesgf cocbustionfglowingaloss-of-coolantaccident.y N $uSe ks"k $lIsI5nh vies t$
ack'Nal k5ESEESEe.lyzerin8EEatedkn YrNEII**
the oxygen ana oxygenbyvo3ume.
i The occurrence of primary systez leakage following a major refueling outage er etber scheduled shutdewn is much more probable than the occurrence of the loss-ef-coolant accident upon Wich the specified oxygen concentration limit is based.
Permitting access to the drywell for leak inspections dur.ing a startup is judged prudent in terms of the added ytant safety of fered without significantly reducing the margin of asfaty. Thus, to preclude the possibility of. starting the reactor and operating for extended periods of tlse with significant leaks in the primary system, leak inspections are scheduled during startup periods, een the primary systen is at or near rated te=perature and pressure.
The 24-hour period to provide inerting is judged to be sufficient to perform the leak inspection and establish the required oxygen concentration. The primary conteirnent is normally slightly pressurised during periods of reactor operation.
Witrogen used for inerting could leak out of the containment but air could not leak in te increase oxygen concentration. Once the contaiment is filled with sitrogen to the required concentration, no monitoring of oxygen concentration is necessary. Bowever, at least once a week, the oxygen concentration will be determined as added assurance.
In conjunction with the Mark 1 Containment Short Term Program, a plant unique analysis was performed (Reference 5) which demonstrated a factor of safety of at least two for the weakest element in the suppression chamber support system and attached piping. The maintenance of a drywell-sup;,ression chamber differential pressure of 1.20 psid and a suppression chamber water level corresponding to a downcomer sub=ergence range of 3.21 to 3.51. feet will assure the integrity of the suppression chamber when subjected to post-LOCA suppression pool hydrodynamic forces.
3.
Standby Cas Treatment System The standby gas treatment system is designed to filter and exhaust the reactor building atmosphere to the chimney during secondary containment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs. One standby gas treatment system circuit is designed to automatically start upon containment isolation and to maintain the reactor building pressure at the design negative pressure so that all leakage should be in-leakage.
Should one circuit fail to start, the redundant alternate standby gas tragtnent circuit is designed to start automatically. Each of the two circuits has 100% capacity. Only one of the two standby gas treatment system circuits is needed to cleanup the reactor building atmosphere upon contaim ent isolation. If one system is found to be inoperable, there is not insediate threat to the containment system performance.
Therefore, reactor operation or refueling operation may continue while repairs are being made. If neither circuit is operable, the plant is placed in a condition that does not require a standby gas treatment system.
While only a small amount of particulates are released from the primary containment as a result of the loss-of-coolant accident, high-efficiency particulate filters before and af ter the charcoal filters are specified to minimize potential particulate release to the environment and to preve -t clogging of the charcoal adsorbers. The 3.7/A.7-13 Amendment No. H,96
e-8[grea
%~g UNITED STATES t
NUCLEAR REGULATORY COMMISSION P-i
.E WASHINGTON, D. C. 20555
/
I COMMONWEALTH EDISON COMPANY AND TOWA-ILLINDIS GAS AFD ELECTRIC COMPANY DOCKET NO. 50-765 OVAD CITIES NUCLEAR POWER STATION, UNTT ?
AMENDMENT TO FACILITY OPERATINr LTCENSE Amendment No. 92 license No. 9PR-30 1.
The Nuclear Reculatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Eriison Company (the licensee) dated November 1, 1982, complies with the standards and requirements of the Atomic Eneroy 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 reculations of the Commission; C.
There is reasonable assurance (i) that the activities authorized 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 reculations and all applicable requirements have been satisfied.
2.
Accordinoly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
t.
.p.
B.
Technical Soecifications The Technical Specifications contained in Appendices A and 53, as revised throuah Amendment No. 92, are hereby incorporated in the f
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 REGIILATORY COMMISSION Ch. N
) John A. Zwolinski, Direc or
( BWR Project Directorate #1 Division of BWR Licensing Attachtrent:
Chances to the Technical Specifications Date of Issuance: August 15, 1986 e
ATTACHFENT TO LICENSE AMENDMENT NO. 92 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET fiO. 50-?ft i
Revise the Appendix A Technical Specifications bv removing the pages
/
identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of chance.
REMOVE INSERT 3.7/4.7-6 3.7/4.7-6 3.7/4.7-6a 3.7/4.7-6a 3.7/4.7-13 3.7/A.7-13 l
l l
I w
t, QUAD-CITIES Drm-se 8 ' '* '
f'h dication and alarm systems
/
- 3) Vacuum breaker posiden in-shan be enlibrated and hac-
- 3) The position alarm sysum will annunciau in se sentrol alonaDy asseed.
"*" " "' M N"f
- 3) At least 25% of the vacuum saceeds abe equivalent o breaken ahan be laspected l/16 lach at all points along each that au vacuum breaken the seal surthee of the disk.
ahD hve hen W M-
- b. Any procure suppression cham-lowing every burth afueling ber drywell vacuurn breaker may estage. If de6ciencies an be non kily closed as indicated by hund, all vacuum breakers the position indication and alarm shall be inspected and den-ciencies correewd.
systems provided that drywell to suppression chamber diferential
- 4) A drywell to suppression Pnssun decay rate k demon-chamber leak inst shau dem-strated to be not gnawr than 35%
enstrate that with initial dir-of the diferential pressure decay hrentid pun of a less rate for all vacuum breakers open enn th % ee difemdd she equivalent of 1/16 inch at all
,g, Pomts along the seal surface of the exceed the rate which would ectur through a 1 inch orince without the addition of air or Reactor operation may continue c.
prended that no more than one nitrogen.
quarwr of the number of pressure esppression chamber drywell vac-sum breakers an determined so be inoperable provided that they are secured er known to be in the closed position.
- d. If failure occurs in one of the two-position alarm systems for one or mon vacuum breakers. sorctor operation may sentinue proiided Ibst a diferential pressure decay ate nest is initialad immediately and performed every 15 days therenner antil the kilum is sor-seesed. The inst shall meet the n-quirements of Speci$ cation 3.7 A 4.b.
- 3. Osygen Consentration
- 5. Osygen Concentration
- a. AAer completion of the startup The primary containment osygeninn-sentration shall be measured and n-sent program and demonstration et plant electrical output, the pri-sorded on a werkly basis.
mary emelainment atmosphere l
shs2.1 he rakseed so 3ess than 44 Em09en by woLane with nitrogen gas sharing resetor poser operation enth eeneter ecolant preasse above Du psig i
Amendment No. 92 11/41-4
.- =
t.
QUAD-CITIES DPR-30 I
axcept as specified in Specification 3.7.A.S.b.
b.
Within the 24-hour period subse-
/
quent to placing the reactor in the Run mode following a shutdown, the containment atmosphere oxygen concentration shall be reduced to less than 4% byvolume, and main-tained in this condition. Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
6.
CONTAINMENT SYSTEMS
- 6. Containnent Systens Drywell-Suppression Chamber Drywell-Suppression Chamber Differential Pressure Differential Pressure a.
The pressure differ-a.
Differential pressure ential between the between the drywell and drywell and suppression suppression chamber shall chamber shall be recorded be maintained at equal to at least once each shift.
or greater than 1.20 psid except as specified in (1), (2), and (3) below:
(1) This differential shall be established within the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period subsequent to placing the reactor mode switch into the RUN mode during a startup and may be relaxed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reactor shutdown when the provisions of 3.7.A.5(b) apply.
(2) This differential may be decreased to less than 1.20 psid for a maximum of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during required operability testing of the HPCI system pump, the RCIC system pump, the drywell-pressure suppression chamber vacuum breakers, and reactor pressure relief valves.
Amendment No. f6 92
SAD =CITit$
DPR 30 h;4 regen, if it is present ir eruffielent quantities to result h excessively rapid geecabitation, could tesult in o less of contaiment intogrity.
The 41 oxygen concentration bv volume minimites the possibility of hydrogen combustion following a loss-of-coolant accident.
k y"N$uEe N"5 $5Is[$nt% int $Signigicantquanitiesg[f ESS E0k br aEba ESeoxygenanalyze$ nEba$edkn oxygenbyvoSume.
r he occurrence of primary system leakage following a major refueling outage or ctber scheduled shutdown is such more probable than the occurrence of the loss-of-coolant accident upon whieb the specified oxygen concentration limit is based.
Permitting er :ess to the drywell for leak inspections dur.ing a startup is judged prudent in terms of the added plant safety offered without significantly reducing the margin of safety. Thus, to preclude the possibility of starting the reactor and operating for extended periods of time with significant leaks in the primary system, leak inspections are scheduled during startup periods, when the primary j
systes is at or near rated ta=perature and pressura.
The 24-hour period to provide inerting is judged to be sufficient to perfora the leak inspection and establish the required oxygen concentration. The primary contaiment is normally alightly pressurieed during periods of reactor operation.
Bitrogen used for inerting could leak out of the containment but air could not
~
leak in to increase oxygen concentration. Once the contairement is filled with altrogen to the required concentration, ne monitoring of crygen concentration
)
is necessary. Ecvever, at least once a week, the orygen concentration will be determined as added assurance.
l In conjunction with the Mark I Containment Short Tern Program, a plant unique analysis was perforted (Reference 5) which demonstrated a factor of safety of at least two for the weakest element in the suppression chamber support i
system and attached piping.
The maintenance of a dryvell-suppression chamber differential pressure of 1.20 psid and a suppression chamber water level corresponding to a downconer submergence range of 3.21 to 3.54 feet will assure the integrity of the suppression chamber when subjected to post-LOCA suppression pool bydrodynar.ic forces.
3.
Standby Cas Treatment Systen 1
The standby gas treatment system is designed to filter and exhaust the reactor butiding atmosphere tcc the chimney during secondary contaiment isolation conditions, with a minimum release of radioactive materials from the reactor building to the environs. One standby gas treatment systes circuit is designed to automatically start upon containment isolation and to maintain the reactor building pressure at the design negative pressure so that all leakage should be in-leakage. Should one circuit fail to start, the redundant alternate standby gas treatment circuit is designed to start automatically. Each of the two circuits has 100% capacity. Only one of the two standby gas treatment system circuits is needed to cleanup the reactor building atmosphere upon contaiment isolation. If one system is found to be inoperable, there is not inmediate threat to the containment system performance.
Therefore, reactor operation or refueling operation may continue while repairs are being aide. If neither circuit is operable, the plant is placed in a condition that does act require a standby gas treatment systes.
While only a small amount of particulates are re7 eased free the primary contairment as a result of the less-uf-coolant accident, high-efficiency particulate filters before and af ter the charcoal filters are specified to minimize potential particulate release to the envirc neent and te prevent clogging of the charcoal adsorbers. The Amendment No. M 92 3.7/4.7-13
_. _ _ _ _ _