ML20108B353
| ML20108B353 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/29/1996 |
| From: | Imbro E NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20108B357 | List: |
| References | |
| NUDOCS 9605030283 | |
| Download: ML20108B353 (8) | |
Text
.,
e1 psorg A *,
UNITED STATES j
y*
s j
NUCLEAR REGULATORY COMMISSION 1
WASHINGTON, D.C. m
- %***,*/
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280-SURRY POWER STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated January 30, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules ano 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 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 public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; S.
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.
9605030283 960429 PDR ADOCK 05000200 p
. 2.
As dingly, 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-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 209, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
!L-
[
dhk M t
Eugene V. Imbro, Director Project Directorate II-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 29,1996 i
4
gARffig UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
\\...../
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0, 50-281 SURRY POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 209 License No. OPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated January 30, 1996, complies with the standards and requirements of the Atomic Energy 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 regulations of the Commission; C.
There is reasonabic assurance (1) 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 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.
J
5
. 2.
Accordingly, 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-37 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications containr.d in Appendix A, as revised through Amendment No. 209, are hereoy incorporated in the license.
The licensee shall operata the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION 1
LS SC Eugene V. Imbro, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance:
April 29,1996
w ATTACHMENT TO LICENSE AMENDMENT AMENOMENT NO.
209 TO FACILITY OPERATING LICENSE NO. OPR-32 AMENDMENT NO.
209 TO FACILITY OPERATING LICENSE N0. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
1 Remove Paaes Insert Paaes TS 3.1-21 TS 3.1-21 TS 4.1-10 TS 4.1-10 TS 4.1-10a TS 4.1-10a i
?
i 5
i e
i
TS 3.1-21 4.
Concentrations of contaminants in the reactor coolant shall not exceed the following maximum limits when the reactor coolant temperature is below 250 degrees F:
l Normal Concentration Transients not to Contaminant (PPM) exceed 24 imurs (PPM) i
- a. Chloride 0.15 1.5 l
1 j
- b. Fluoride 0.15 1.5 l
4 2
If the limits above are exceeded, the reactor shall be immediately brought to i
COLD SHUTDOWN and the cause of the out-of-specification condition shall be l
l ascertained and corrected.
i 5.
For the purposes of correcting the contaminant concentrations to meet Technical Specifications 3.1.F.1 and 3.1.F.4 above, incmase in coolant temperature consistent j
with operation of primary coolant pumps for a short period of time to assum mixing j
l of the coolant shall be permitted. This increase in temperature to assure mixing shall in no case cause the coolant temperature to exceed 250 degrees F.
l 6.
For conditions above COLD SHUTDOWN, if more than one contaminant or l
contaminants transient, which results in contaminant levels exceeding any of the normal steady state operation limits specified in 3.1.F.1 or 3.1.F.4, is experienced in any seven consecutive day period, the reactor shall be placed in COLD SHUTDOWN l
until the cause of the out-of-specification operation is ascertained and corrected.
j I
i i
t 4
Amendment Nos.
209 and 209 d
.ma4,.
44..m
+.g,rgg
,aJ-..+e
.e+J nmm..
_dasa.J a.am _4J_4aa..
...m_J
,4h,.
4ne aw-#a'._
a_
a an.
auogn
-m an.m.aae.-
..a
+__
TS 4.1-10 f
i i
i l
TABLE 4.1-2B MINIMUM FREQUENCIES FOR SAMPLING TESTS 4
FSAR SECTION DESCRIFTION TEST FREOUENCY REFERENCE i
1 1.
Reactor Coolant Radio-Chemical Monthly (5)
Liquid Samples Analysis (I)
)
Gross Activity (2) 5 days / week (5) j Tritium Activity Weekly (5) j
- Chemistry (CL, F & O )
5 days / week (9) l.
2 9*g
- Boron Concentration
'Puice/ week i
E Determination 8'"I*"" dY Once/2 weeks (5)
DOSE EQUIVALENTI-131 s
Radio-iodine Once/4 hours (6) l Analysis (including I-131, and (7) below I 133 & I-135)
I 2.
Refueling Water Storage Chemistry (Cl & F)
Weekly 6
3.
Boric AcidTanks
- Boron Concentration Twice/ Week 9.1 i
4.
Chemical Additive Tank NaOH Concentration Monthly 6
i 5.
Spent Fuel Pit
- Boron Concentration Monthly' 9.5 6.
Secondary Coolant Fifteen minute degassed b Oncen2 hours 10.3 and q activity DOSE EQUIVALENTI-131 Monthly (4)
Semiannually (8)
I 7.
Stack Gas Iodine and
- I-131 and particulate Weekly Particulate Samples radioactive releases i
i
- See Specification 4.1.D (1) A radiochemical analysis will be made to evaluate the following corrosion products: Cr-51, Fe-59, Mn-54, Co-58, and Co-60.
(2) A gmss beta-gamma degassed activity analysis shall consist of the quantitative measurement of the total radioactivity of the primary coolant in units of pCi/cc.
Amendment Nos. 209 and 204
3 TS 4.1-10a 1
l (3)
E determination will be staned when the gross gamma degassed activity 1
of radionuclides with half lives greater than 15 minutes analysis indicates 210 pCi/cc. Routine sample (s) for 5 analyses shall only be taken after a minimum of 2 EFPD and 20 days of power operation have elapsed since reactor was last subcritical for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or longer.
i
)
(4) If the fifteen minute degassed beta and gamma activity is 10% or more of the limit given in Specification 3.6.E, a DOSE EQUIVALENT I-131 analysis will be performed.
(5) When reactor is critical and average primary coolant temperature 2350 F.
(6) Whenever the specific activity exceeds 1.0 Ci/cc DOSE EQUIVALENT I-131 or 100/5 Ci/cc and until the specific activity of the Reactor Coolant System is restored within its limits.
(7) One sample between 2 & 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a THERMAL POWER change exceeding 15 percent of RATED POWER within a one hour period provided the average primary coolant temperature 2350 F.
(8) When the fifteen minute degassed beta and gamma activity is less than 10% of the limit given in Specification 3.6.E.
(9) Sampling for chloride and fluoride concentrations is not required when fuel is removed from the reactor vessel and the reactor coolant inventory is drained below the reactor vessel flange, whether the upper internal and/or the vessel head are in place or not. Sampling for oxygen concentration is not required when the reactor coolant temperature is below 250 degrees F.
Amendment Nos. 209 and 209