ML20033B029
| ML20033B029 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/13/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML20033B027 | List: |
| References | |
| NUDOCS 8111300298 | |
| Download: ML20033B029 (4) | |
Text
r METROPOLITAN EDISON COMPAhi JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 103 (Rev.1)
This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No.
DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPAhT By Dire'ctor, TMI-1 Sworn and subscribed to me this / 3 day of Werw~[c 1981.
c, C
O Notary P'blic CATHY BREY, Notary tic Londonderry Twa.. Dauphin County. Pa.
Mf Comrnission Empires Oct. 24.1933 M Oh
i UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION J
IN THE MATTER OF F
DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY 4
This is to certify that a copy of Technical Specification Change Request No.103 (Rev. 1) to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given'below, been filed with the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania and Dauphin Conty, Pennsylvania by deposit in the United States mail, addressed as follows:
i' Mr. Donald Hoover, C'. airman Mr. John E. Minnich, Chairman Board of Supervisors of Board of County Com=issioners Londonderry Township of Dauphin County R.D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 i
METROPOLITAN EDISON COMPAh7 By
\\
Director, TMI-l i
+
Dated:
Mnem cer-/{,//f/
f p
g._
I?[. %
Technishi Specification Change Request (TSCR) No. 103, Rev. 1
~ -
The licensee requests that the attached changed pager replace all proposed C# changed Pages in TSCR 303 (original).
H. r Reasons For TSCR 103, Rev. 1 1.
The pages for TSCR 103 (original) have been revised to reflect oral conments as a result of NRC review.
The changes are itemized below.
In addition, current Technical Specification pages (Thru Admendment 74) have been incorporated.
1.
A margin bar has been added to the fifth paragraph on page 2-7 to reflect a corrected typographical error from a previous TS Amendment.
2.
TS 3.1.12.4.b has been revised to add an action state =ent.
3.
TS 3.1.12.4.c has been added 4.
TS 3.4.1.d has been revised to add an action statement.
5.
Foctnotes in Table 3.5-1 (item B) have been revised to specify reactor power and connect the footnotes for bistable performance.*
6.
Table 3.5-1 has been revised to:
a.
Add a new item C.3.F.,
b.
Split item C.6 into C.6.a and C.6.b, c.
and add footnote f 7.
Footnotes in TS 3.5.3.1 have been revised to specify the correct valves for reset of the bypass permissive bistables.
S.
Table 3.5-2 has been revised to indicate the correct aumber of channels consistent with the latest design and specification 3.1.12.
9.
TS 3.5.5.1 has been revised to require action in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> for l
pressurizer level and the bases for this TS has been revised accordingly.
I 10.
TS 3.20 (3.19 in original submittal) 11.
Table 4.1-1 has been revised to include a new item 19.c and revise l
item 45 and 48 footnotes.
12.
Specification 4.9.1.2 has been clarified.
13.' TS 4.9.1.4 has been revised to be consistent with Table 4.1-1 item 31.
14.
TS 4.9.1.6 has been expanded to require a test to a shutdown greater than 30 days in lieu of once each refueling.
15.
A new specification 4.6.3 has been added and items 6 and 7 from Qf 4.6.1.b have been moved to 4.6.3.
z+
~
m.
~.,
1 16.
Typographical errors have been corrected in footnotes on page 3-105 i
?
and specification 3.5.1 has been referenced in Action 27.
i g ;_
an.
?l> ',., n ;
OAx c LJ 5-
.I_Z_i.z Safety Evaluation Justifying Change I
The safety evaluations for TSCR 103 (original) remains valid except as discussed below for items 7 and 14 presented above.
Item 7 - The nominal setpoints for the HPI and LPI bypass permissive bistables are set conservatively (to accommodate instrument tolerance).
The former footnotes did not accommodate bistable dead band and instrument tolerance (drift and repeatability).
(Dead band is the difference between bistable trip and bistable reset.) This change is adminis-trative in nature to avoid misinterpretation of these footnotes.
Item The Licensee had proposed a test of the EFW system flow path on a once per refueling basis as a backup to stringent administrative controls and syste= alarms (alarn on auto start) and EFW flow indicators designed to assure EFW will be supplied when required in the event of an accident (EFW is not needed and not used for normal plant startup and shutdown).
The NRC requires that this surveillance be conducted for any shutdown greater than 30 days.
Since this surveillance cannot be conducted at IMI-1 without adding oxygenated water to the Stea= Generators (SG) these tests should be minimized.
(Oxygen in the SG is related to SG tube degradation.)
Shutdowns between refuelings are infrequent, especially shutdowns greater than 30 days,.therefore, the nu=ber of times this surveillance will be conducted is not expected to differ significantly from the number conducted for refuelings during the plant life.
On this basis the Licensee believes the NRC proposed frequency is acceptable.
If, however, experience show this not.to be the case, the Licensee vill request that this specification be reviewed accordingly.
Implementation Where new equipment is involved cycle 5 startup testing must be completed to demonstrate compliance with certain proposed TS.
In order to avoid compliance difficulties in light of this fact, the Licensee requests that these IS become The Licensee will nevertheless effective upon exceeding 5% reactor power.
implement the TS prior to greater tiaan 5% power and subsequent to NRC approval where it is possible and appropriate.
License Fee (10 CFR 70.22)
This is a revision to a previously requested TSCR 103 and therefore is covered as described therein.
- It should be noted that during natural circulation testing, to be performed as of the Cycle 5 startup test progra= the sensitivity of the reactor power (power range) indicator will be increased such that the actual " indicated" part power is 10 times less than the apparent reactor power (i.e. 50% power read on the meter equals 5% indicated power).