ML20198C351
| ML20198C351 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/14/1986 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20198C327 | List: |
| References | |
| NUDOCS 8605220401 | |
| Download: ML20198C351 (5) | |
Text
__.
-[e ne o,,
UNITED STATES F
NUCLEAR REGULATORY COMMISSION o
g l
WASHINGTON, D. C. 20555
\\,*****/
SAFETY EVALUATION SY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 92 TO FACILITY OPERATING LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION DOCKET N0.50-029
1.0 INTRODUCTION
By letter dated May 26, 1981, as revised January 23, 1984 and February 26, 1985, the Yankee Atomic Electric Company (YAEC) submitted a request for changes to the Yankee Nuclear Power Station Technical Specifications (TS).
The amendment modifies the TS for: (1) Safety injection tank temperature; (2) the steam generator blowdown monitor setpoint; (3) containment isolation boundaries; (4) Emergency Core Cooling System (ECCS) surveillance require-ments; (5) the reactor vessel wall fluence exposure curve; (6) the Carbon activeEfflbe)ntTS. system; (7) the Plant On-Site Review Committee; and (8) Radio-Dioxide (C0 2.0 EVALUATION 2.1 SAFETY INJECTION TANK TEMPERATURE The licensee requested to raise the minimum <olution temperature in.
the safety injection tank (SIT) from 40*F to 120 F.
In addition, the proposed change would place an upper limit of 130 F on the SIT solution temperature. This change is intended to reduce the thermal stresses on the reactor vessel following safety injection after a postulated severe transient. Analysis performed by Yankee Atomic Electric Company (YAEC) and indepondent analysis performed by the staff in its evaluation of the pressurized thermal shock (PTS) phenomenon, (Generic Issue A-49) show that raising the temperature of safety injection water is an effective means of reducing any possible consequences of a postulated PTS transient.
This temperature band is also sufficiently low enough to ensure current design basis analyses are not affected.
%[2ggg{ @
p P
, Concurrent with this change, the licensee requested to modify the surveillance frequency for verifying the SIT temperature by removing reference to an outside air temperature. The current TSs do not require verification of SIT temperature unless the outside air temperature is below 35'F. Verification of SIT temperature is now required every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> regardless of outside air temperature.
Based on these evaluations, the staff finds the proposed changes acceptable.
2.2 STEAM GENERATOR BLOWDOWN MONITOR SETPOINT The licensee requested to increase the steam generator blowdown monitor alarm setpoint from 80 counts per second (CPS) (equal to 4800 counts per minute (CPM)), to 6000 CPM.
This change was requested when the existing-GM-tube detectors were replaced by more sensitive Sodium Iodine Detectors.
Background levels with the old detectors _ran approxima.tely 10 CPS (600 CPM),
while background with the new detectors runs approximately 1500 CPM. Given the difference in background levels measured by the different detectors, I
the new setpoint provides a level of detection of abnormal steam line radiation levels (approximately 4500 CPM above background) approximately equal to the level of detection provided by the old detectors (approximately 4200 CPM above background).
Based on this evaluation, the staff finds the proposed change acce~ptable.
2.3 CONTAINMENT ISOLATION 1
l The licensee requested to: (1) remove a manually operated valve from the l
list of valves that need to be open for the main coolant system safety l
valve flow path; and (2) to modify the terminology used to refer to containment isolation conditions.
For item (1), the plant modification i
that removed the Low Pressure Surge Tank (LPST) as part of the containment l
boundary also modified the main coolant safety valve discharge flow path.
l This modification is discussed in NUREG-0825 " Integrated Plant Safety l
Assessment, Systematic Evaluation Program," for the Yankee Nuclear Power Station. The discharge of the valves is now directed to the containment through a rupture disc, instead of the old flow path through valve PR-V-608 to the LPST.
PR-V-608 is, therefore, no longer required to be locked open and should be removed from the TS that verifies the safety valve discharge flowpath. This change is, therefore, acceptable.
Current TS use inconsistent terminology in referring to containment isola-tion conditions. The amendment provides consistent terminology, and provides reference to the applicable TS section that defines the required containment isolation condition. This change is administrative in nature, and does not change any existing TS requirements.
Based on these evaluations, these changes are acceptable, k
d
. 2.4 ECCS SURVEILLANCE REQUIREMENTS The licensee requested to remove one of the listed valves that are
. currently identified as being required to be open for long-term ECCS recirculation cooling in a post-LOCA environment.
In its November 14, 1978 letter that forwarded Amendment 52 to the Yankee TS, the staff.
approved modification of the recirculation flow path, including the installation of new piping that would provide for use of the ECCS pumps for recirculation, instead of using the charging pumps. This modification removed CH-MOV-523-from the recirculation flow path, and as such ie no longer J
required to be verified open for this flow path. The staff, therefore, finds it acceptable to delete CH-MOV-523 from the list of valves required for verification of the recirculation flowpath.
2.5 REACTOR VESSEL WALL FLUENCE The licensee requested to modify the bases graph depicting reactor vessel i
fluence as a function of cumulative power generation. The proposed graph, based on the latest fracture analysis performed for the Yankee vessel by Westinghouse, provides an increased fluence for a given amount of power generated, resulting in a more restrictive upper limit pressure temperature curve than the current curve provides. This proposed curve.
has been determined to be more restrictive, and is acceptable.
2.6 CO,, SYSTEM The licensee requested an exception to the requirement that the high pressure CO, system be operable in Manhole No. 3 (Diesel Generator Building) whenever equipment in the manhole is required to be operable.
The exception would allow the C0 system to be disabled whenever maintenanceisbeingconductedibthemanhole. The current TS requires, i
whenever the CO, system is inoperable, that a continuous fire watch be posted within ohe hour, and a special report submitted within 30 days'if the CO, system cannot be restored within 14 days. The exception would require; a continuous fire watch to be posted, and the CO system must i
2 remain capable of being manually initiated, whenever the exception is used.
The staff finds that the exception provides at least the same level of protection for the equipment in Manhole No. 3 as the current TS, and merely removes the special report requirement when pre-planned maintenance is being conducted.
The change is, therefore, acceptable.
~
2.7 PLANT OPERATION REVIEW COMMITTEE The licensee requested to modify the administrative section of the TS that specifies the composition of the Plant Operation Review. Committee 1
(PORC). The proposed change would designate the on-site Technical Director as second Vice Chairman for the PORC, and changes the quorum j
.._.. ~...-___. - - - - - _ _,_.D
J 4-requirements to incorporate the second Vice Chairman. A quorum is still specified as at least a total of six (6) people, with at least a Vice Chairman present.
Standard Westinghouse TS only identify a Chairman position, and allow the Chairman to designate an alternate. This designation policy is consistent with ANS 18.7-1976, Section 4.3.2.3, that specifies that the " Chairman (or his duly appointed alternate) shall be present for all formal meetings."
The licensee's proposal effectively pre-designates who can act for the Chairman.
The Licensee's proposed change is more restrictive than the Westinghouse Standards TS and the guidance contained in ANS 18.7-1976, and provides the necessary expertise at all PORC meetings. The Licensee's proposed change is, t
therefore, acceptable.
2.8 RADI0 ACTIVE EFFLUENT TS FLOW MEASURING DEVICES The licensee proposes to add an " Applicability" column to the list of Radioactive Liquid Effluent Monitoring Instrumentation, and require instrument operability for continuous composite samplers and flow rate measurement devic'es only when flow exists in the specified systems. This change updates the TS to require radioactive effluent monitoring only under conditions that provide something to be measured.
This change continues to assure monitoring of any possible release of radioactive effluents, and does not modify any monitoring of radioactive effluents that the current 1S accomplish.
The proposed change is, therefore, acceptable.
In addition, the licensee proposes to add an additional radioactive effluent instrument, the Steam Generator Blowdown Tank Effluent Flow Rate Measurement Device, to the list of required instrumentation. This proposed change adds additional monitoring capability to the current TS, and is, therefore, acceptable.
I 2.9 TECHNICAL SPECIFICATIONS NOT ISSUED The following requested actions from Proposed Change 139 Supplements 4 and 5 are not approved, since either inappropriate technical justification was provided or the staff finds the requested change inappropriate. These f
changes are Supplement 4, item 15, and Supplement 5, items 8, 26, 27, 28, 30 and 38a.
If the changes addressed in these are still required or desired, a new proposed change should be submitted based on the current TS pages.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves a change to a requirement with respect to the installation or use of facility components located within the restricted
~
area as defined in 10 CFR Part 20 and changes to the surveillance require-j ments.
1 i
c
,-,-s.,y,9,,_m__.
---w----,,=y-w--,.
.,,-_.p,.,,.. -.- _,_,.,
s..p.,
__,.,_,,.,,----,g_-%
___.-.w,
,_,,.m.,_._,.--r-,
.-- e
5-The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner;.and (2) public such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT Principal Contr.butor:
J. W. Clifford Dated:
May 14, 1986 e
g
--yw-p a-
.,,p 9 f, g *-. gw-c g- - - -
w,y,.p-
-w y.-94w,4,g-4.,.
,,wp-_,
c.w-%g 4,ef-t w