ML20148E714
| ML20148E714 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/21/1988 |
| From: | Mihalcik J BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-67143, NUDOCS 8803250284 | |
| Download: ML20148E714 (5) | |
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ALTIMORE GAS AND ELECTRIC CHARLES CENTEFi. P.O. BOX 1475 BALTIMORE, MARYLAND 21203
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. NUCLEAR ENGINEERING SERVICES DEPARTMENT
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March 21, 1988' l
U. S. Nuclear Regulatory Commission Washington,DC 20555 ATTENTION:
Document Control Desk i
SUBJ ECT:
Calvert Cliffs Nuclear Powcr Plant Unit No. 1; Docket No. 50-317 Partial Withdrawal of Proposcid Technical Specification 3.1.1.1. Unit L (TAC NO. 67143)
REFERENCES:
(a)
Letter from Mr. J.A. Tiernan (BG&E), to Document Control
)
Desk (NRC), Docket Nos. 50-317 and 50 318, "Request for Naendment Unit 1 Cycle 10 License Application," dated Februgry 12, 1988.
Centlenen:
1 I
We understand that one of the proposed Technical Specification changes submitted in the Unit 1 Cycle 10 reload request for license amendment (Reference (a)), is currently under generic review by the NRC staff, pending a resolution in the future. This particular pcrtion of the proposed change is not required for operation of Unit 1 Cycle 10, therefore we request to withdraw that portion.
Specifically, all changes proposed for page 3/4 1-1 of Technical Specification 3.1.1.1, should be withdrawn, except the reference to Figure 3.1 lb. The withdrawal of these proposed changes replaces applicability of Technical l
Specification 3.1.1.1 to the critical Modes of operation. By this withdrawal,
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the page n.anber for Figure 3.1-lb will change from the proposed 3/4 1-2 to 3/4 l-2a.
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The attached copies of Technical Specification 3.1.1.1 *indiente the effect of
- his withdrawal on the proposed changes of Reference (a).
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Certain changes to the Bases, as suomitted in Reference (a), also result from this. withdi:aval action. These will be submitted via separate correspondence.
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March 21, 1988 Page 2 cc:
D. A. Bruno, Esquire J. E. Silberg, Esquire R. A. Capra, NRC S. A. McNeil, NRC W. T. Russell, NRC D. C. Trimble, NRC T. Magette, DNR
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!!3/4.1 REACTIVITY CONTROL SYSTEMS
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!!3/a.1.1 EORATION CONTROL I I 0
- ! SHUTDOWN MARGIN - T
> 200 F r
avg 1
LIMITING CONDITION FOR OPERATION eqpal to er greater then Ne liw.it line of i 3.1.1.1 The SHUTOOWN MARGIN shall be i 3. : P :.';/ k.
F/p-c 3./-16.
AFPlICABILITY:
MODES 1, 2", 3 and 4
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r less ther fhe limit line of Fipre 3 l-lb,,
With the SHUTDOWN HARGIN - 3.5%' J.k/k5 imediately initiate and continue l
boration at > 40 gom of 2300 ppm boric acid solution or equivalent until
- ne requirec SHUT 00WN MARGIN is restored.
- l i,
i ll, SUR'JEILLANCE REOUIREMENTS y etual to or gree ter thin the lin,it line ef Aquee 3.l-l b :,
,s 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to bel :.5?._;/k;
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a.
Within one hour af ter detection of an inoperable CEA(s) and at least l
once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the CEA(s) is inoperable.
If the inoperable CEA is imovable or untrippable, the above required SHUT-DOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the irrovable er untrippa.ble CEA(s).
b.
When in MODES 1 or 2, at least once per 12 hcurs by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.
I c.
When in MODE 2-~, within 4 neurs prior to achieving reacter critical-ity by verifying that the predicted critical CEA positicn is within the limits of Specification 3.1.3.6.
l c.
rior :: initial cperatien above 5% RATED THERMAL POWER after each l
fuei icading, by considera:icn of the facters of e belcw, witn the
{ [j CEA gr0ups at the Transien; Inse-tion Li.its cf $;ecification 3.1.3.5.
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- Adnerer.cs to Technical Scecifica:icn 3.i.3.6 as s;ecified in Surveillance Recuirements a.1.1.1.1 assures that tnere is sufficien; avail (ble shutdown margin to maten the shutdown margin requirements of the safet) analyses.
"See 5;ecial Test Exceptien 3.10.1.
'l # With X.,>er, 1.0.
=5Witn Kgff < i.0.
- AL'iERT C'.IFFS - L' NIT 1 3/" 1-1 Amendmen: No. 12, 7 7, 22,104
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c.
REACTIVITY CONTROL SYSTEMS-SURVEILLANCE REQUIREMENTS (Continued)
When in MODES 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by con-e.
sideration of the following factors:
i 1.
Reac. tor coolant system boron concentration;.-
2.
CEA position, 3.
Reactor coolant _ system average temperature,
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d.
Fuel burnup based on gross thermal energy generation,-
S.
Xenon concentration, and.
6.
Samarium concentration.
The overall core reactivity balance shall be comoared to 4.1.1.1.2 predicted values to demonstrate agreement within + 1.0% tk/k at least once per 31 Effective Full Power Days (EFPD).
ThTs comparison shall l
consider at least those factors stated in Specification 4.1.1.1.1.e, The predicted reactivity values shall be adjusted -(normalized) above.
to correspond to the actual core conditions prior to exceeding a fuel burnup of 60 Effective Full Power Days after each fuel loading.
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CALVERT CLIFFS - UNIT 1 3/4 1-2 i
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9 c4g 6.0
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ACCEPTABLE J
0?tRATION 5.0 REGION (E0C,5.0}
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+s na 4.0 Y
MINIMUM SilUTDOWN MARGIN o
(80C,3.5)
- 0';.%^0
- 0 2 p c.0),2 a t:0 =
ys ocI 3.0 4e i
z to 3
p g
UNACCEPTABLE t;
OPERATION 5
REGION 2.0 E
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1.0 M
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BOC EOC TIME IN CYCLE Figure 3.1-lb
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