ML19317G653
| ML19317G653 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/12/1975 |
| From: | Davis E, Kaplan D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8003250708 | |
| Download: ML19317G653 (13) | |
Text
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- TRIBUTION FOR PART 50 DOCKE 1 ATE RI AL (TEMPOR ARY FORM)
CONTROL NO:
3100 FILE:
FROM: SMUD DATE OF DOC DATE REC'D LTR TWX RPT OTHER Sacramento, Calif.
95813 gy rw c.
3-12-75 3-24-75 XX TO:
ORIG CC OTHER SENT AEC PDR XX Mr. A. Giambusso 1 siened 39 SENT LOCAL PDR W
CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXX XXX 40 50-312 DESCRIPTION:
Ltr notari::ed 3-12-75 requestinc ENCLOSURES:
Proposed Change No. 1 to for Change No. 1 to Techt Specs for Rancho Sec o' Tech Specs for Rancho Seco....
& trans the following:
f (40 cys encl ree'd)
PLANT N AME: Rancho Seco FOR ACTION /iNFORMATION DHL 3-24-75 BUTLER (L)
SCHWENCER (L) ZIEM ANN (L)
REG AN (E)
W/ Copics W/ Copies W/ Copies W/ Copies CLARK (L)
STOLZ (L)
DICKER (E)
LEAR (L)
W/ Copic3 W/ Copies W/ Copies W/ Copies PARM (L)
V ASSALLO (L)
KN!GH TON (E)
SPELS W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L)
YUR9LE (L)
YOUNGBLOOD (E)
W/ Copies W(gCopies W/ Copies W/ Copies INTERNAL DISTRIBUTION NCG C"D TECH _ REVIEW DENTON LIC ASST A/T IN D_.
FNnC PUR SChROED E R GRIMES R. DIGGS (L)
B R AITM AN W6GC, ROOM P E06A MACCARY GAMMILL H. GE ARIN (L)
SALTZMAN WOSSICK/ STAFF KNIGHT KASTN ER E. GOUL BOURNE (L)
ME LTZ CASE PAWLICKl BALLARD P. KREUTZER (E)
GI AM BUSSO SHAO SPANGLER J. LEE (L)
PLANS _
BOYD STELLO M. MAIGRET (L)
MCDONALD MOORE (L)
HOUSTON ENVIRO S. REED (E)
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IPPOLITO KNIGHTON M. SLATER (E)
PETERSON P. CO L LINS TEDESCO YOUNGBLOOD H. SMITH (L)
HARTFIELD (2)
DENISE LONG
,fEGAN S. TEETS (L)
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,3EG OP3 LAINAS PPROJECT LDR G. WILLI AMS (E)
EISENHUT WILE & FTEGION (2)
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WIGGINTON T.R. WILSON VOLLMER HAR LESS R. INGRAM (L)
STEELE 64/V EXTERN AL DISTRIBUTION
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'~' SACRAMENTO MUNICIPAL UTIUTY DISTRICT C 6201 S Street, Box 15830, Sacramento. California 95813: [91 March 12, 1975 s
Mr. Angelo Giarbusso, Director Division of Reactor Licensing
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Nuclear Regulatory Commission Washington, D. C.
20545 ggh x',
Re: NRC Docket No. 50-312, Proposed Technical Specification Change No. 1, Rancho Seco Nuclear Generating Station,
~W Unit No.1
Dear Mr. Giambusso:
In accordance with 10 CFR 50.59, the Sacramento Municipal Utility District hereby proposes to change its Technical Specifications for Rancho Seco Nuclear Generating Station, Unit No.1, by submitting forty (40) copies of Proposed Technical Specification Change No.1.
The purpose of the proposed change is to revise the Technical Specifi-cations Section 3.5 and Section 3.12 to permit power operation at the rated level of 2772 MRt.
The attached changes are for operating conditions up to and af ter 100 effective full power days.
An additional submittal will be forwarded for operation at rated power af ter 75 effective full power days.
The additional data will con'sist of figures, similar to Figure 3.5.2-1B and 3.5.2-2B and appropriate text changes. We do not feel that this would prevent evaluation of this proposed change at this time since the analysis of the later data will be identical to that contained in this change.
The additional changes will be forwarded to you in approximately two weeks.
Proposed Change No. I will change the Technical Specifications in the following areas:
1)
Page 3-32, Section 3.5.2.4. A(1) rewritten to:
" (1)
If four reactor coolant pumps are in operation, the allowable thermal power shall be reduced by 2 percent of maximum allowable power for each 1 percent tilt in excess of 4 percent. !bsimum allowable power is defined in Tech-nical Specifications Section 1.1.
The allowable thermal m3 j -[/-
power is defined in Figures 3.5.2-LA and 3.5.2-1B where the power level cutoff applies during transient xenon
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operation. "
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Mr.1 Ang1L9 Giambusso '
' March 12,1975
'a 2):
Page 3-33,~ Section 3.5.2.5.C:
" Figure ~ 3.5.2-1A for the first 100 EFPD 'of operation and figure -
-3.5.2-1B thereaf ter" was added to the ~ first L sentence.
3)
Page }-33, Section 3.5.2.5.D:
"of figures 3.5.2-1A and 3.5.2-2B" was added to define where the cutoff is described.
4)
..Page 3-33, Section 3.5.2.5.D(1)1 and (2) were reworded for clarity to:
"(1) 2hnon reactivity is within 10 percent of the equilibrium value.for operation at the maximum power level (94.9% or 100% as ' applicable) and asymptotically approaching stability.
This l condition must be satisfied for a xenon free startup.
or
"(2)'
The reactor power shall be held for a minimum of two hours within a band extending from 5%FP below Power Level Cutoff up to Power Level. Cutoff of figures 3.5.2-1A and 3.5.2-1B."
5)
. Page' 3-33a, Section 3.5. 2. 6:
" Figure 3.5.2-1A for the first 100 EFPD of operation and figure
- 3.5. 2-2B thereaf ter.
If the imbalance is not within the envelope
. defined by the appropriate figure 3.3.2-2A or 3.5.2-2B" was added.
O Page 3-33a, Bases:
The first sentence was revised to include the additional figures 3.5.2-2A and 3.5.2-28.
This was done twice in the first paragraph.
3:
7)
Page 3-33a, Bases:
The control rod group overlap was correct to read "25 percent t 5 percent."
Group 8, ' the word has been changed' from " bank" to " rods" to agree with plant nomenclature.
8)-
Page 3-33b:
- The-sixth; paragraph has changed "89% to 94%" to the band extending ifrom 5%FP below the power level cutoff up to power level cutoff.
~
9)
- Figures 3.5. 2-1A, 3. 5. 2-1B, 3.5.2-2A, and 3.5.2-2B were added.
10)\\ l Figures 3.5.2-1 and. 3.5.2-2 should be' removed from the present '
~
- Technical. Specifications.'since they are obsolete.-
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l Mr. Angelo Giambusso March 12, 1975
- 11) Section 3.12 should be removed from the present Technical Specifications since it no longer applies.
Respectfully submitted, SACRAIENTO MUNICIPAL UTILITY DISTRICT W
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' ' A'N By General Manager l dL l' hijlID3. KAP' General Couns of Sacramento Mu cipal Utility District Subscribed and sworn to before me this 12th day of March, 1975.
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$I "Y MATTIER,\\ Notary Public in and for BET County of Sacramento, State of J-a pj '
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NTO @ kcommission expires January 12,19h6.
Oo 310m OLP1RD
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
'Y,[!}'
3.qg.7f Limiting Conditions for Operation F.
If a control rod in the regulating or axial power shaping groups is declared inoperable per Specification 4.7.1.2, operation above 60% of rated power may continue provided the rods _in the group are positioned such that the rod that was declared' inoperable is maintained within allowable group average position limits of Specification 4.7.1.2 and the with-drawal limits of Specification 3.5.2.5.c.
- 3. 5. 2. 3 The worth of a single inserted control rod shall not exceed 0.65 percent Ak/k at rated' power or 1.0 percent Ak/k at hot zero power except for. physics testing when the requirement of Specification 3.1.8 shall apply.
3.5.2.4
' Quadrant tilt:
A.
Whenever the q c4 cant power tilt exceeds 4 percent, except for physics tests, the quadrant tilt. shall be reduced to less than 4 percent within two hours or the following actions shall be taken:
(1)
If four reactor coolant pumps are in operation, the allowable thermal power shall be reduced by 2 percent of maximum allowable power for each 1 percent tilt in excess of 4 percent.
Mtximum allowable power is defined in Technical Specifications Section 1.1.
The allowable thermal power is defined by Figures 3.5.2-1A and 3.5.2-13, 1
where the power level cutoff may apply during transient zenon operation.
(2).
If less than four reactor coolant pumps are in operation, the allowable thermal power shall be reduced by 2 percent of maximum allowable power for each 1 percent tilt below the power allowable for the reactor coolant pump combin-
- s.
ation.
(3)
Except as provided in 3.5.2.4.b, the reactor shall be brought to the hot shutdown condition within four hours if the quadrant tilt is not reduced to less than 4 per-cent af ter 24' hours.
-(4)
The. power range high. flux set point shall be reduced 2 percent of the maxinum allowable flux for the RC pump combination for each 1 percent tilt in excess of 4 per-cent.
B.
If the quadrant tilt ' exceeds 4 percent and there is simultaneous indication of a misaligned control rod per Specification 3 5 2 2 reactor operation may continue, provided power is reduced to 60 percent of the daermal power allowable for the reactor coolant pump combination.
3-32 M
RANCHO SECO UNIT 1 TECHNICAL $?ECIIICATIONS Limiting Conditions for Operation i
- C.
Except for physics tests, if quadrant tilt exceeds 9 percent, the reactor _ shall be brought to the hot shutdown condition within four hours.
D.-
Whenever the reactor is. brought to hot shutdown pursuant to
- 3.5.2.4a(3) or '3.5. 2. 4. c above, subsequent reactor operation is permitted for the purpose of measurement, testing and corree-tive action provided the thermal power and the power range high flux setpoint allowable for the reactor coolant pump combination are restricted by a reduction of 2 percent of maximum allowable power for each 1 percent tilt.
E.
. Quadrant power tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15 percent of rated power.
3.5.2.5 Control Rod Positions A.
Technical Specification 3.1.3.5 _(safety rod withdrawal) does not prohibit the exercising of individual safety rods as required by table 4.1-2 or apply to inoperable safety rod limits in Technical Specification 3.5.2.2.
B.
Operating rod group overlap shall be %5 percent i 5 percent between two sequential groups, except for physics tests.
C.
Except for physics test or exercising control rods, the control rod withdrawal limits are specified on figure 3.5.2-1A for the first 100 EFPD of operation and figure 3.5.2-1B thereaf ter.
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If
_the control rod position limits are exceeded, corrective measures shall be taken incediately to achieve an acceptable control rod position. Acceptable control rod positions shall then be attained within two hours.
D.
Except for physics tests, power shall not be increased above the power level cutoff of figures 3.5.2-1A and 3.5.2-1B unless one l~1 of the following conditions is satisfied:
-(1)
Xenon reactivity is within 10 percent of the equilibrium value for operation at the maximum power level (94.9% or 100% as applicable) and asymptotically approaching stability.
1 This condition must be satisfied for a xenon free startup.
or-I ~(' ) -
The reactor power shall be held for a minimum of two hours 2
. within a band extending from 5%FP below Power Level Cutoff 1
up to Power ' Level Cutoff of. figures 3. 5. 2-1A and 3.5.2-13.
3-33 5
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RANCHO SECO UNIT'1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.5.2.6 Reactor power imbalance shall be monitored on a frequency not to exceed two hours during power op-ration above 40 percent rated power.
Except for physics tests, imbalance shall be maintained within the envelope defined by Figure 3.5.2-2A for the first 100 EFPD of oper-ation and Figure 3.5.2-2B thereafter.
If the imbalance is not within 1
the envelope defined by the appropriate figure, 3.5.2-2A or. 3.5.2-2B, corrective measures shall be taken to achieve an acceptable imbalance.
If an acceptable imbalance is not achieved within two hours, reactor power shall be reduced until imbalance limits are met.
l1 3.5.2.7 The' control rod drive patch panels shall be locked at all times with limited access to be authorized by the superintendent or his designated representative.
Bases The power-imbalance envelope defined in Figures 3.5.2-2A and 3.5.2-2B is based l1 en LOCA analyses which have defined the maximum linear heat rate (see figure-3.3.?-3) such that the maximum clad temperature will not exceed the Interim Acceptanco Criteria.
Operation outside of the power imbalance envelope alone does not constitute a situation that would cause the Interim Acceptance Criteria to be exceeded should n LOCA occur.
The power imbalance envelope represents the boundary of operation limited by the Interim Acceptance Criteria only if the control rods are at the position limits as defined by figures 3.5.2-1A and 3.5.2-1B and if a 4 percent quadrant power tilt exists.
Additional consertatism y
is introduced by application ~of:
A.
Nuclear uncertainty factors.
B.
Thermal calibration uncertainty.
C.
Fuel densification effects.
E D.
Hot rod manufacturing tolerance factors.
The'25 percent overlap between successive control rod groups is allo'wed since.
l1 the worth of a rod is lower _at the upper and lower nort of the stroke.
Control rods are arranged in groups ~ defined as follows:
l1 Group Function 1
Safety 2
Safety 3
Safety 4-Safety 5'
Regulating 6
-l Regulating 7~
Regulating 8
APSR (axial power shaping rods) 3-33a-Amendment 30
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Control rod groups ar'e withdrawn in sequence beginning with group 1.
Group 5 is overlapped 25 percent with groups 6 and 7, which operate in parallel. The normal position at power is for groups 6 and 7 to be partially inserted.
. The minimum available rod worth provides for achieving hot shutdown by reactor trip at any time assuming the highest worth control rod remains in the full out position.
(1)
Inserted rod groups during power operation will not contain single rod worths greater than 0.65 percent ak/k.
This value has been shown to be safe by the safety anslysis of the hypothetical rod ejection accident.
(2) A single inserted control rod worth of 1.0 percent ak/k at beginning of life, hot, zero power would result in a lower peak thermal power and therefore less severe environmental consequences than 0.65 percent ak/k ejected rod worth at power.
The quadrant power tilt limits set forth in Specification 3.5.2.4 have been established within the thermal analysis design base using the definition of quadrant power tilt given in Technical Specifications, Section 1.6.
These limits in conjunction with the control rod position limits in Specification 3.5.2.5c ensure that design peak heat rate criteria are not exceeded during normal operation when including the effects of potential fuel densification.
The quadrant tilt and axial imFalance monitoring in Specifications 3.5.2.4 and 3.5.2.6, respectively, normally will be performed in the process computer.
The two-hour frequency for monitoring these quantities will provide adequate surveil-lance when the computer is out of service.
Allowance is provided for withdrawal limits and reactor power imbalance limits to-be exceeded for a period of two hours without specification violation.
Accept-able rod positions and imbalance must be achieved within the two-hour time period or appropriate action such as a reduction of power taken.
Operating restrictions are included in Technical Specifications 3.5.2.5d (1) and 3.5.2.5d (2) to prevent excessive power peaking by transient xenon.
The xenon reactivity must either be beyond the "undershoot" region and asymptotically approaching its equilibrium at rated power or the, reactor must be operated for a minimum of two hours within a band extending from 5% FP below power level cutoff 1
.up to power level cutoff in the soluable poison control mode so that the transient peak is burned out at a lower power level.
During physics testing, additional safety margins are provided by administratively setting special reactor protection system limitations. During the power. ascension testing program, the following high_ flux trip setting will be set prior to in-creasing to the next plateau.
3-33b
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s uMCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
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Limiting Conditions for Operation
-l
-Test Plateau Level %
Overpower Trip %
0
<5 15~
50 40 50 75 95 90 100 100 105.5
' REFERENCES
_(1) FSAR, paragraph 3.2.2.1.2
. (2).FSAR, paragraph:-14.'2.2.4-3-33c Amendment 30 L
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i 100 (180.3,96.9)
(195.6,96.9) 90 POWER LEVEL CUT 0FF 87.4 %
(179.3,87.4)
>(200,s7.4) 80 (172,77.9) 70' Restricted g
Region x
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50 sD g
(122.3,40.9) w i
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Permi ssi bl e Operating 20 Region (80,14.3) 10
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O 20 40 60 80 100 1 20 140 160 180 20 0 Rod index, 7, Wi thdrawn 0
25 50 75 100 I
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O 25 50 75 100 Group 6 & 7 I
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Group 5 1.
Rod index is the percentage sum-of the withdrawal t
of control rod groups 5,6 & 7 2.
The restrictions on rod position are in effect up to 100 EFPD.
The restrictions are modified af ter 100 EFPD as shown in Fi gu re 3. 5. 2-18 ROD POSI TION LIMITS
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l 100 (180.3,102) 9 (195.6,102) 90 POWER LEVEL CUT 0FF 92 %
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(179.3,v2)
(172,82) 80 70 Restricted g
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g Permi ssi bl e Operating 2
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25 50 75 100 i
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25 50 75 100 Group 6 & 7 I
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Group 5 1.
Rod index is the percentage sum of the withdrawal of control rod groups 5,6 & 7 2.
The restrictions on rod position are in effect after 100 EFPD R00 POSITION LIMITS rtAfwu n ftJL A Jtn
s, I20 l
I i10 RESTRICTED REGION 100
- 19. 4, f:6. 9
+7.0,96.9 90
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30 20 10 0
-60
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+20
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+60 Core imbalance,1,
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1.
The limits are in ef fect up to 100 EFPD.
The limits after IOO EFPD are shown in Fi gu re 3. 5. 2-28 OPERATIONAL POWER IMBALA.1CE EN V ELO P E Fi gu re 3. 5. 2-2A
T I 20 l
l l10 RESTRICTED
-20.4,102 REGION 100
+7.6,Io2 r
i 90
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y 40 2
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- 1. The limi ts are in ef fect af ter 100 EFPD.
OPERATIONAL POWER I MB AL AN CE ENVELOPE Fi gu re 3. 5. 2-28