ML20099C614
| ML20099C614 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20099C616 | List: |
| References | |
| DPR-50-A-102 NUDOCS 8411190605 | |
| Download: ML20099C614 (7) | |
Text
f549'c6 UNITED STATES e
- [
^[ i NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555 3....
j METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICEN.cE Amendment No. 102 License No. DPR-50 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by GPU Nuclear Corporation, et al (the licensees) dated June 4, 1984, as supplemented August 8, 1984,-
complies with the standards and requirements'of the Atomic Energy' Act of 1954, as amended (the Act) and the-Comission'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 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.
8411190605 841031 PDRADOCK05000g j
1 4
2.
.Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license mendment, and paragraph 2.c.(2).of Facility Operating License No. DPR-50 is hereby amended to read as follows:
Technical Specifications The Technical Specificatio t contained in Appendix A, as revised through Arr. " Ant No.102, are hereby incorporated in the license. GPU Nuclear Corporation shall operate:the facility in accordance with the Technical Specifi. cations.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION n
\\
I Johh F. Stolz, Chief Op4 rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 31, 1984 W*
ATTACHMENT TO LICENSE AMENDtiENT NO. -102 FACILITY OPERATING LICENSE N0. DPR-50 DOCKET ' t!0. 50-289 Replace'.the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical 1.ines indicating the area of change.
Remove Insert 3-41 3-41
,4-3 4-3 6-22 6-22 6-23 6-23 I
e t
*6+'i' A,g,p..
g.m r
1 3.6 REACTQR BUILDING Acclicability Applies to the contairrnent integrity of the reactor building.
Objective To assure containment intagrity
'Soecifications 3.6.1 '
Containment integrity, as defined in Section 1.7, shall be maintained whenever all three of the following conditions exist:
a.
Reactor coolant pressure is 300 psig or greater.
b.
Reactor coolant temperature is 200*F or greater.
c.
Nuclear Fuel is in the core.
3.6.2 Containment integrity snall be maintained when oath the reactor coolant system is open to the containment atmosphere and a shutdown margin exists that is less than that for a refueling snutdown.
3.6.3 Positive reactivity insertions which would result in a reduction in.
shutoown margin to less than IX Ak/k snall not be made by control rod motion or baron dilution unless containment integrity is being maintained.
3.6.4 The reactor shall not be critical whenr tne reactor building irkternal t
pressure exceeds 2.0 psig or 1.0 psi vacuum.
3.6.5 Prior to criticality following refueling shutdown, a check shall ce made to confirm that all manual containment isolation valves wnien should be closed are closed and are conspicuously marked.
If, while the reactor is critica)., a reactor building isolation valve i
3.6.6 is determined to be inoperaole in a position other than tna required i
position, the other reacter ouilding isolation valve in the line shall be tested to insure operability. If tne inoperable valve is not restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the operaole valve will be closed or the reactor shall'oe brought to the cold shutdown condition witnin an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.6.7 The hydrogen recomoiner shall be operable during REACTOR CRITICAL, 4
L HOT STAN08Y and POWER OPERATION. With the nydrogen recomoiner inoperable, restore the recomoiner to operable status or bring the reactor to HOT SHUTDOWN within seven (7) days.
i 3-41 Amencment No. 57,102 l
l
t I
t s
p
. t a
r u e'e y
5 eeo i
% a r
5 echb 0
t t i t
1 h n 6
af v ar r l a e t
nal e e n
u r
n e
a v w a
cs p u
h nB e o h
l r h
t u np t
a e e S
rt e cbh r
ah n r
mt f
.er e wo e
r a ost eH r
t eh n e aw.dt a
wci e u e e o
h gr eo nu r pt me r r prt it g f r n go ei rl o c
r ww t a se sohf d e n oo i t e r e l i t l e ef t
c et c
n pr a r pa
.r g ad o ti e e e ct en end nr wr peinwi r a et o bd eos t
e e p% e ncpu 5 r o cc dne 5 cl i r 5 en ii r1 nl er e
.1 p
v v eg o
oa e pocn pf r r pat e
hd t no eui e e et cvk s e ocai v s s dl a o c e wal L ot p no eb e nct e aeb e u. nn i v r ah o x rb t ast sii r
S cie n mn f r y se nn t
a nie nf a a nn T
N S
ed e e ea eh e me ot d e e d nhh cr ct h y uh s
h h E
K H
R uuWW nb n Wf rWl nW W l
al a e it ah e C
A R
H cd
) ) l l l r) r s) ic v) )
I C
nn1 2 a aa o1 e n2 x a e1 1 U
R I a( ( b cb m( vi( a ee( (
Q E
R 1 E
- C 1 N C
. A T
4L A
)
)
L R
A A
2 2
EI S
N N
(
(
A A i R R
LE I
)
HN8 DV L
1 AR A
(
I U C
M S
I N
E T
M S
U E
A R
T H
M N
M PPM H
T S
N K
I C
)
) )
E 1
1 1 H
A A
(
( (
C N
N O
S S 5 S S
S e
l r
e u
n t
n a
a r
r h
e e
Cl p t
N l
l e m n
t O
l f
e e ne a
n I
e c e l
n g nT l
a.
I niv i
n na o! l l P
ngi p
a ah t oe oe I
a or m
h R C n C n on R
hL D A
C a
nC n C
C r
eel r a d
S ed e e e
t go oh rh E
nc ok g g
a no t C oC D
onR a n n
i ac c
t i e e a a
dR a ec e L
t d l rR R
e rl e r a r E
ci oD me oeR u e u N
ec r r
r r ct n sR s N
t nt pe e
e r c nh s s
A ol nl w w
t u a a ge we H
r oor o o
no ehi r or C
PCCI P P
I SR C HP L P 1
2 3
4 5 67 8
9 eOro J
. h.
m yw
(
I 2
- j q'
I
c.
documentation that the changes have Deen r:, viewed cn'd approved pursuant to 6.8.2.
2.
Shall become effective upon review and approval oy GPUNC Management.
6~.14 CFFSITE DOSE CALCtLATION MANUAL (00CM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.
6.14.2 GPU Nuclear Corporation initiated changes to the 00CM:
1.
Shall be sucmitted to the NRC in the Semiannual Radioactive Erfluent Release Report for the period in which the changes were made. This suomittal sna11 contain:
sufficiently detailed information to justify the changes without a.
benefit of additional or s@plemental information; b.
a determination that the changes did not reduce the accuracy or reliacility of dose calculations or setpoint determinations; and c.
documentation that the changes have been reviewed and approved pursuant to 6.8.2.
i 2.
Shall become effective @on review and approval by GPUNC Management.
6.15 Deleted 6.16 POST-ACCIDENT SAMPLING PROGRAMS NUREG'0737 (II.B.L II.F.1.2)
Pro rams which will ensure the capability to accurately sample and ana yze vital areas under accident conditions have been implemented.
The following programs have been established:
1.
Iodine and Particulate Sampling 2.
Reactor Coolant Sampling 3.
Containment Atmosphere Sampling Each program shall be maintained and shall include tne following:
i 1.
Training of personnel,,
2.
Procedures, and 3.
Provisions for maintenance of samoling and analysis eculament.
4 i
i 110/24/00 Order, Amendment No. 'rf,JM 102 6-22 d
,,,-.._..,..,,-e..,,
..-n, e..
6.17 MAJOR CHANGES TO RADIOACTIVE WASTE TREATMENT SYSTEMS 6.17.1 GPU Nuclear Corporation initiated safety related changes to the radioactive waste system (liquid, gaseous and solic):
1 Shall be reported to the Connission in the Annual Report l
(Specification 6.9.18) for the period in which the evalu-ation was reviewed. The discussion of each change shall i
contain:
a.
A summary of the evaluation tnat lec to the determina-tion that the change could be made in accorcance with 10 CFR 50.59; b.
Sufficient detailed information to total ly support the reason for the change without benefit of additional or supplemental information; A detailed description of the eculpment, components and c.
processes involvec and the interf aces with other plant systems; c.
An evaluation of tne enange whicn shows the predicted releases of racioactive materials in licuic anc gaseous effluents anc/or cuantity of solid waste that differ from those previously predicted in the license application anc amencments thereto; e.
An evaluation of the change whien shows the exoec?ec maximum exposures to incivicuals in the unrestricted area anc to the gene.'ai peculation ?na? differ f rom hose creviously estimated in the license aco!ication anc amencments thereto; t.
A comparison of the precicted releases of radioactive materials, in licula anc gaseous eftfuents and in solic
)
waste, to the actual releases for the perioc crior ?c.nen l
the changes are to be mace; g.
An estimate of the exposure to Diant operating personnel as a result of the change; and h.
Documentation of the fact that the change was reviewec anc l
Amendment No.JP;8,102 6-23