ML20028E565
| ML20028E565 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/20/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa Illinois Gas & Electric Company |
| Shared Package | |
| ML20028E566 | List: |
| References | |
| DPR-29-A-085 NUDOCS 8301280014 | |
| Download: ML20028E565 (6) | |
Text
.
+
mesu
'k USH7s0 STATES
[*
NUCLEAR REGULATORY COMMISSION o
5 WASHieeGT0el, D. C. 30046 C00910NWEALTH EDIS0N C09 ANY go IOWA ILLIN0IS GAS D ELECTRIC COWANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT'l' AENDENT TO FACILITY OPERATING LICENSE Amendment No. 8 5 -
License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated December 20, 1982 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules 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 pubife, 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 requirements -
have been satisfied.
2.
Accordingly, the license is amended by changes to thii Technical Spec-ifications as indicated in f e attachment to this license amendment i' '
and paragraph 3.B of Facilir. License No. DPR-29 is hereby amended to read as follows:
B.
Ty hnical Specifications
~ ihe Technical Specifications contained in Appendices A and B, as revised through Amendment No.&5, ar6 hereby incorporated in the license. The licenge shall operate the facility in accordance with the Technical Specifications.
P
m
. 3.
"Within 90 days after the effectiva date of this amendment, or such later time as the Commission may specify, the Licensee shall satisfy any applicable requirement of P.L. 97-45 related to pur-suing an agreement with the Secretary of Energy for the disposal of high-level radioactive waste and spent nuclear fuel."
4.
This license amendment is effective as of December 2.0 ::1982.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: January 20, 1983 9
Attachment to License Amendment No. 8 5 To Facility Operating Liccase DPR-29 Docket No. 50-254
' Revise Appendix A Technical Specifications as fol.1.ois:
Remove Insert 3.7/4.7-3 3.7/4.7-3 3.7/4.7-4 3.7/4.7-4 3.7/4.7-10 3.7/4.7 10 l
l
- (
1" e
., "W h s :Xn-
\\
GUAD CITIE5 DPR-29
- b. If any periodic Type A test b) fL l.0 percent by weight fails ta mest either O.75 Le ts of the containment air per or 0.75 Lt. the test schedule 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pres-for subsequent Type A tests sure of P, 25 psig, shall be reviewad ent! approved t
by the commission.
If two 2)
A combined leakage rate of consecut.ive Type A tests fail t4
.$ 0.60 L for all penetra-meet eather 0.75 La or 0.75 tionsan$ valves,exceptthe L, e Type A test shall be main steam isolation valves, performed at leost every 18 and the M01-220-1 valve sonths until two consecutive (while it is inoperable), sub-Type A tests meet either 0.75 or 0.75 L, at which time j
ject to Type B and C tests L
t ths above test schedule any be when pressurized to Pa.
The H01-220-1 valve will be resumed.
restored to operability no later than startup after the
- c. The accuracy of each Type A test first Cold Shutdown following shall be verified by a a 30 day period after December supplemental test whicht 21, 1982 l
- 1) Confirms the accuracy of the l
J) 11.5 sef per tioarr for any one test by verifying that the main steam isolation valve difference between the l
.when tested at 25 psig.
supplemental data and the l
Type A test data is within
- b. With the measured eyerall.
0.25 La or 0.25 L.
t Integrated containment leakage
, rate exceeding 0.75 Le or 0.75
- 2) Has a curation sufficient.to L, as applicabis, restore the establish accurately the -
t overall integrated leakage change in leakage rate rate (s) to 5 0.75 La or S 0.75 between the Type A test and L, as applicable.
the supplemental test.
t
- c. With the measured combined
- 3) Requires the quantity of gas leakage rate for all injected into the containment per4atrations and valves, except or bled from the containment for main steam isolation valves, during the supplemental test subject to Type B and C tests to be equivalent to at least I
l exceeding $.60' La, restore the-25 percent of the total l
combined leakage rate for all measured leakage et Pee 48 p.sig, or P. 25 psig.
penetrations and valves, except t
for main steam isolation valves, s Jbject to Type 8 and C tests
- d. Type B and C tests shall be to 0.40 La-conducted at Pa, 48 psig, et intervals no greater' than 24 months tw;ot for to'sts d.. Leakage shall be 21mited to a leakage rate of less then or involvings ~
equal to 3.75 percent of L" I
- 1) Air locks, which shall be.
for any one air lock when pressurized to ld psig.
testrd at 10 psig at least once per 18 months, and,-
Fmendment pY,8-5
(
3.7/4.7-3
m w u-.a + 6
,...v.-
GUA0 CITIES DPR-27 o
- o. With the measured leakage rate
- 2) Main steam isolation valves, exceeding 11.5 scf per hour for which shall be leak tested at any one main steam. isolation least once per la months et a valve, restore the leakage rate pressure of 25 psig.
to 5 11.5 scf per hour for any i
one main staan isolation vaJye
- 3) Bolted double-gasketed seals prior to increasing the reactor which shall be tested at a coolant temperature above prestyre of 48 psig whenever i
2120F.
the seal is closed after keing opened and each operating cycle.
\\
4)
While valve M01-220-1 is inoperable, valves M01-220-2 M01-220-3, and M01-220-4 shall be VERIFIED closed after each closure.
- e. All test leakage rates shall be calculated using observed data converted to absolute values.
Error analyses shall be l
performed to select a balanced t
integrated leakage measurements system.
~-
!3. Pressure Suppression Chamber-Reactor Building vacuum Breakers
- 3. Pressure Suppression Chamber-
, Reactor Building Vac6um Ereakers o, Except as specified in Specification 3.7. A.3.b below,
- a. The pressure suppression l
two pressure sup-chamber-reactor building vacuum ov l
l
~
. -. =
- 3* U'*7-0 Amendment No. N' g 8 5
,s 7;., m y,
' gygn_cgyggy 3. '-
Dr.2-29 o
r.
(
2)
- v. -
' s,*
.t sie m3ae. boladon.==hs
~
(one at a time) shalik semi-god gbr closus des..
.c s
~
't ~'
- d. At kast swice pr weeb the main
- sseamllae poweroperated hole.
sien valves shat be saeselsed by parda! slosse and embaspent 880PenIng.
2; Men en bobiton valve Nted inTa-
- 2. In the event any isolation valve spei-bk 3.71 Is inoprobic,the posiden or Sed in Table 33-t becs.snes inopess-st kast one other valva la soth line -
bk.seactor power operation may ase-1aving an inoperabk vaht shan be
~
ainee provided at Icast one wahr is secorded dany.
sachline havinganinope ablewaktis In the mode correspnding to the be-l Asied condition.*
- 1. If Spetincations 33.D.1 and 33.D.2 sannot be met, an orderly shmadown shall b: laitiated and the scactor shan be la the cold shutdown condidoa
~
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
e'
- 4. The tesaperature of the main susE
- line air pilot vafves shall be less than 110' F aacept as sp;cined in Spe:iA-canons 33.D.5 anJ 3.7.D.6 below.
- 5. F om and after the date that the tem-perature of any main steamfir:e air -
pilot valve is found'io be greater 'than
.170' F. seactor operadon is permissi-b:e only during the succeedins 7 day,,
l unless the temperature of such valve is
. sooner reduced to less than 170' F.
l l.
provided the main secastine isolation valves are operable.
- 6. ITSpecincation33.D.$ cannotbesnet.
I she main steamline isolation valve f
s!.all be considered inoperable sad acdon taken in accordance with Speci.
Station 3.7.D.2.
't During operating cycle 7, until valve NO-220-1 is restored to.
o7erability, valves M01-220-2,3 and 4 will regnain closed, except j
that when the unit is in start-up/ hot standby, valves M01-220-2,
(>
3 and 4 may be opened as needed to drain the steamlines, and as ll.
needed subsequent to Grobp I isolation to clear the isolation.
'T Amendmentflo',ef,85 33fd.w A
_._,,,,.-..-,.