ML20101G020
| ML20101G020 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/19/1992 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20101G018 | List: |
| References | |
| NUDOCS 9206250263 | |
| Download: ML20101G020 (4) | |
Text
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- Attachment IV to ET 92-0121:
Page 1 of 4 ATTACllMENT IV PROPOSED TEC11NICAL SPECIFICATION CllANGF,S L
Y 9206250263 920619 DR ADOCK 050004G2 p
Attachrent IV to ET 92-0121 Page 2 of 4 TABLE 3.3-6 ' Continued)
TABLE. NOTATIONS
- With fuel in the respective fuel storage pool.
- With irradiated tuel in the fuel storaga areas or fuel building.
3
- Trip Setpoint concentratit.3 value ( C1/cm ) is to be establithed such that the actual submersion dosc rate would not exceed 2 mR/h in the control room.
I
- Trip Setpoint concentration value (pci/cm ) is to be established such that 3
tne actual submersion dose rate would not exceed 4 mR/h in the fuel building.
3
- Trip Setpoint concentration value (pci/cm ) is to be established such that the actual submersion dose rate would not exceed 9 mR/h in the containment buildtpg A a--Satne h be incycase_d up to the equivalent limits of " :-i'ic;ti n 3 21.-2. 2 S ction 3.1 of th_e _ODCs)in accordance with the methodo ogy and parame era in Du during containment purge or vent provided the Setpoint value does not exceed twice the maximum concentration activity in the containment determined he eemple erformed prior to each release in accordance with Tabl 3-1 of the ACTION STATEMENTS ACTION 26 - With less than the Minimum channels OPERABLE requirement, opera.
tion may continue provided the containment purge valves are main-tained closed.
ACTION 27 - With the number of OPERABLE channels one less than the Minimum Channels OPERAL'LE requirement, isolate the Control Room Emergency Ventilation System and initiate operation of the Control Room Emergency Ventilation System in the recirculation mode within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within I hour.
ACTION 28 - With less than the Minimum Channels OPERABLE requirement, opera-tion may continue for up to 30 days provided an appropriate portable continuous monitor with the same Alarm Setpoint is provided in the fuel area.
Restore the inoperable monitors tc OPERABLE ctatus within 30 days or suspend all operations involving fuel movement in the fuel building.
ACTION 29 - Must satisfy the ACTION requirements for Specification 3.4.6.1.
ACTION 30 - With the number of CPERABLE channels one less than the Minimum Channels OPERABLE requirement, isolate the Fuel Building Ventila-tion System and initiate operation of the Emergency Exhaust System to maintain the fuel building at a negative pressure within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or with no OPERABLE channels within I hour, i
WOLF CREEK - U1IT 1 3/4 3-41 Amendment No. 10
j Attachnient IV to ET 92-0121 i
Page 3 of 4 ADMINISTRATIVE CONTROLS i
j 6.3 UNIT STAFF OUALI? CATION (Continued)
)
b.
The position of Radiation Protection Manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.
c.
The NSRC 3mbers shall meet or exceed the requirements of ANSI /ANS 3.1-1981.
6.4 TRAINING 6.4.1 A ratraini.u and replacement training program for the unit staff ahall be i
maintained under the directie-if the hanager Training and shall meet or exceed the requirements and recommenmations of Section 5 of ANSI /ANS 3.1-1978 with the followirg exceptions.
a.
The training program for Licensed operators and Senior Operators shall 3
l meet or exceed the requirements and recommendations of Section 5 of ANSI /ANS 3.1-1981 as endorsed by Regulatory Guide 1.0, Revision 2, and 10 CFR Part 55.
b.
Training shall include familiarization with r-levant industry operational experience identified by the 7"'A or another plant-group.
f5 REVIEW AND AUDIT 6.5.1 PLANT SAFETY REVIEW COMMITTEE (PSRC)
FUNCTION i
6.5.1.1 The PSRC chall function to advise the Director Plant Operations on all matters related to nuclear safety.
COMPOSITION i
6.5.1.2 The PSRC shall be composed of then j
Member:
Manager '
"gginccrirg *:-lf CrcckSystem Engineering Member Manager Operations l
Member Manager Technical Support i
Member:
Manager Maintenance and Modifications I
Member:
Manager Instrumentation and control Member:
Supervisor Reactor Engineering Member Manager Radiation Protection Member:
Manager Chemistry l
Member:
Supervisor Results Engineering i
Chairman:
Manager Plant Support l
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the PSRC Chairman to serve on a temporary basis; however, no more than tuo alternates shall participate as voting members in PSRC activities at any one time.
I i
l WOLF CREEK UNIT 3 6-7 Amendment No. 20,25,45,-54 i
l fl 4
l Attachment IV to ET 92-0121 Page 4 of 4 ADMTNISTRATIVE CONTROLS ff0CEDURES AND PROGRAMS (Continued) 6.8.3 Changes to Procedures a.
Temporary changes to Major krocedures, of the categories listed in Specification 6.8.1 which do not change the intent or generate an unreviewed safety question of the original or su' sequent approved procedure, may be made provided such changes to operating procedures are approved by the Shift Supervisor (SRO licensed) and one-of the cha s
- ' o P
_edures_under Call Superintendents.
m groups other than Operations ( e. g. M a' int'e nsnc'e,"'%g the 'ur s -+i no nstrumentat'on a
. Control, Reactor En ineerins Chemistry, et-Health Ph sics whic do not change e in ent or generate an unreviewe s e question, changes may be made upon approval of the Cognizant Croup Leader and a Call Superintendent.
All temporary changes to Major Procedures (made by a call Super-intendent and either a cognizant Group Leader or the Shift Supervisor) shall subsequently be reviewed by the PSRC and approved by the Director Plant Operations within 14 days, except that temporary changes to Major Proceduret made during a refueling outege ma*/ be reviewed and approved at any time prior to initial criticality of the reload core.
All permanent changes to Major Pr;eedures shall be made in accordance E
with Specification 6.8.2.a.
b.
All temporary or permanent changes to Minor Operating Procedures (checkoff lists, alarm responses, data sheets, operating instructions, etc.) shall be approved bv the sbift Supervisor, and shall be subse-quently reviewed and appt=4 red by the Operations PSRC Subccmmittee.
All terporary or perm e t ch n a to ot ar i
P oc_edur_es under the iurisdiction c' aroups other than pera ions (e4g.'Mainionance,
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fastrumEntat'i n d. f ntrol Chem gist, er-lealth A P ysics) r shall be ppm, Reactor Epqineering, Cognizant Group L M er and s a a
e sequently reviewed and approved by the appropriate PSRC s
Subcommittee.
c.
Temporary changes to Corporate Emergency Plan implementing procedures may be made provided that (1) the intent of the original procedure is not altered. (2) the change is approved by the Manager Technical Services, and (3) the change is documented, revieued by appropriate Corporate and plant personnel and approved by the President and Chief g
Executive Officer within 14 days of the implementation.
6.8.4 The following progr ams shall be established, implemented, and maintained:
a.
React or Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outsida containment that could contain highly radioactive fluids during a scrious transient or accident to as low as practical levels. The systems include the appropriate portions of the Containment Spray System, Safety Injection System, Chemical and Volume Control System, RHR System, and the Nuclear Samplin; System (PASC m..yi. The program shall include the following:
WOLF CREEK - UNIT 1 6-15 Amendment No.
d, 45 o