ML20074A947
| ML20074A947 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 05/05/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20074A948 | List: |
| References | |
| NUDOCS 8305170019 | |
| Download: ML20074A947 (9) | |
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.S UNITED STATES
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NUCLEAR REGULATORY COMMISSION i
WASHINGTON, D. C. 20555
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PUBLIC SERVICE. ELECTRIC AND GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-311 SALEM NUCLEAR GENERATING STATION, UNIT NO. 2 AMEN,0 MENT TO FACILITY OPERATING LICENSE Amendment No.19 License No. DPR-75 1.
The Nucidar Regulatory Connission (the Commission) has found that:
A.
The application for amendment by Public Service Electric and Gas Company, Philadelphia Electric Company, Delmarva Power and Light Company and Atlantic City Electric Company (the licensees) dated January 31, 1983, 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 appifcation, 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 er.hangering the health and safety of the public, and (ii) that such activ-ities will be conducted in compliance with the Commission's regulations; l-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 l
51 of the Commission's regulations and all applicabix. requiraments have been satis'fied.
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8305170019 830505 PDR ADDCK 05000311 P
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Accordingly, the license i's amended by changes to the Technical 5:ecifications as indicated in the attachment to this license amendment, and paragraph 2,C.(2) of Facility Operating License No. DPR-75 is herehy amended to read as follows:
(2)' Technical Soecifications The Technical Specifications contained in Accendices A and B, as revised through Amendment No.19, are l
herehy incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This 'icense amencment is effective as of the date of its iss'uance.
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"ME NUCLEAR REGULATORY COM.'tISSION 1
- hga, Operating Reacters B,e -
r nch #1 Division of Licensinh A::achment:
Changes to :ne Technical Specifications
~Date of Issuance: May 5,1983 S
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. ATTACHMENT TO LICENSE AMENDMENT NO.19:
FACILITY OPE' RATING LICENSE NO. DPR-75 DOCKET NO. 50-311 e
Revise Appendix A as follows:
Remove Pages In' sert Pages 3/4 2-7 3/4 2-7 S 3/4 2-5 B 3/4 2-5 B 3/4 2 ' 6-17 6-17 6-17a 3/4 1-21 3/4 1/21 e
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P0i'EP DISTRIBUTIO!: LIMITS SURVEILLANCEREOUIREdENTS(Continued) b) At least once per 31' EFPD, whichever occurs first.
2.
When the Fxy is.les's than or equal to the [x limit for the appropriate measured core plane, additional power distribution
'C RTP L
maps shall be taken and Fxy compared to Fxy and Fxy at least once per 31 EFPD.
e.
The F limit for RATE 9 THERMAL POWER (F({P) shall be pr;ovided for xy all core planes containing oank "D" control rods and all unrodded core planes in a Radial Peaking Factor Limit Report per specification 6.9.1.10.
f.
The Fxy limits of e., above, are not applicable in the following core plane regions as mneasured,in percent of core height from the bottom'of the fuel:
1.
Lower core region from 0% to 15%, inclusive.
2.
Upper core region from 85% to 100%, inclusive.
3.
Grid plane regions at 17.8% + 2%, 32.1 + 2%, 46.4% + 2%,
60.6% - 2% and 74.9';
- 2%, inclusive.
4.
Core plane regions within + 2% of core height-(- 2.88 inches) about the bank demand position of the bank "D" control rods.
g.
Evaluating the effects of Fxy on F (Z) to determine if F (Z) q is within its limit whenever Fxy exceeds Fxy-
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4.2.2.3 When F (Z) is measured pursuant to specification 4.10.2.2, an overall Q
measured F (Z) shall be obtained from a power distribution map and increased by Q
.3% to account for manufacturing tolerances and further increased by 5% to
' account"for measurement uncertainty.
SALEM - UNIT 2 3/4 2 7 Amendment No.19 4
4 POWER DIS RIBUTION LIMITS BASES The penalties applied to F H to account for Rod Bow (Figure 3.2-4) as a event.
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function of burnup are consistent with those described in Mr. John F. Stolz's (NRC) letter to T. M. Anderson (Westinghouse) dated April 5,1979 and W 8691 Rev.1 (partial rod bow test data).
When an F measurement is taken, an allowance for both experimental error q
and manufacturing tolerance must be made.
An allowance of 5% is appropriate for a fail core map taken with the incore detector flux mapping. system and a 3%
allowance is appropriate for manufacturing tolerance. When RCS flow rate and F
are maasured, no additional allowances are necessary prior to comparison -
g with the limits'of Figure 3.2-3.
Measurement errors of 3.5% for RCS total flow rate and 4% for F hfve been allowed for in determination of the design DNBR g
value.
The 12 he;r ceriodic su veillance of indicated RCS fleet is sufficient to detect only flow degradation which could lead to operation outside the acceptable region of operation shown in Figure 3.2 3.
The ra:ia: peaking factor Fxy(2) is measured periodically to provide assurance i
that the not channel factor, FQ(z), remains within its limit'.
The F limit for xy Rn RATED THERMAL POWER (Fxy ), as rovided in the Radial Peaking Factor Limit Report per specification 6.9.1.10, was determined from exp'ected power control l
maneuvers over the full range of burnup conditions in the core.
l 3/4.2.4 OVADRANT POWER TILT RATIO The quadrant power tilt ratio limit assures that the ' radial power
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f distribution satisfies the design values used in the power capability analysis.
Radial power districution measurements are made during startup testing and periodicsily during power operation.
SALEM _ U';IT 2 B 3/4 2-5 Amendment No.19 I
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20<.'ER DISTRIBUT:0N LIMITS 5'SES The limit of 1.02 at which corrective action is required provides DNB and linear heat generation rate protect. ion with x-y plane power tilts. A limiting tilt of.1.025 can De to'lerated before the margin for uncertainty in Fq is
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depleted. The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.
The 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a cropped or misaligned rod.
In the event such action does not correct the tilt.
tne cargin for uncertainty on Fq is reinstated by reducing the power by 27. from RATED THERMAL POWER for each percent of tilt in excess of 1.0.
3/4.2.5 DN3 PARAMETERS l
The limits en tne DNS related parameters assure that each of the parameters are maintained tith the normal steady state envelope of operation assumed in the transient and, accident analyses.
The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a i
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'.inum D"S of 1.30 throughout each analyzed transier.:.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are r'estored within their limits following load changes and other expected transient operation.
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1 SALEM _ UNIT 2 B 3/4 2-6 Amendment No.19 i
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ADMINISTRATIVE CONTROLS h.
Errors. discovered in the tr'ansient or accident analyses or in the methods used for such analyses as described in the safety a'nalysis report or in the bases for the technical specifications that have or could have permitted reactor operation in a manner less conservative than assumed in the analyses.
i.* Performance of structures,' systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases; or discovery during unit life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition.
THIRTY DAY WRITTEN REPORTS
. 6.9.1.9 The types of events listed below shall be the subject of written reports to the Adninistrator of the Regional Office within thirty days of occurrence of the event. The written report shall include, as a minimum, a completed copy of a licensee event report form.
Information provided on the licensee event report form shall be supplemented, as needed, by additier31 narrative material to provide complete explanation of the circunstances l
- surrounding the event.
l a.
Reactor protection system or engineered safety feature instrument settings which are found to be less conserva.ive than those estab-lisned by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems.
b.
Conditions leading to operation in a degraded mode permitted by a limiting condition -for operation or plant shutdown' required by a limiting condition for operation.
c.
Observed inadequacies in the implementation of administrative or procedural controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineerea safety l
feature systems.
d.
Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting
.- from the fission process.
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l SALE.1 - UNIT 2 6-17 Amendment No.19 f
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I ADMINISTRE?IVE CONTROLS RADIAL PEAXING FACTOR LIMIT REPORT 6.9.1.10 The F limits for RATED THERMAL POWER (FR P) for all core planes zy containing bank "D" control rods and all unrodded core planes and the plot of predicted (F T,pRel) vs. Axial Core Height with the limit envelope shall be q
provided to the NRC Regional Admini'strator with a copy to Director of Nuclear Reactor Regulation, Attention:
Chief, Core Performance Branch, U.S. Nuclear Regulatory Commission, Washington, D. C. 20555 at least 60 days prior to each cycle initial criticality unless otherwise approved by the Commission by letter.
In addition, in the event that the limit should change requiring a new submittal or an amended submittal to the Peaking Factor Limit Report, it will be submitted 60 days prior to the date the limit would become effe,ctive unless otherwise approved by the Commission by letter.
RT will be by request from the NRC and need Any information needed to support Fxy not be incluoed in this report.
SPECI*L REPORTS 6.9.2 Special reports snall be submitted to the Director of tne Office of i
Inspectior and Enforcement Regional Office within the time period specified for each report
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SALEM - UNIT 2 6-17a Amendment No.19 n
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Fracticn of Rated ihe m l Fewer Figure 3.1-1 ROD EANK INSERTION LIMITS VERSCS THIPS.AL POWER FOUR LOOP OPERATION 3/4 1-21 Amendment No.19 SALEM
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