ML20205R283
| ML20205R283 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 04/01/1987 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20205R278 | List: |
| References | |
| NLS-87-066, NLS-87-66, NUDOCS 8704060297 | |
| Download: ML20205R283 (45) | |
Text
_.
ENCLOSURE 1 TO NLS-87-066 PROPOSF.D TECHNICAL SPECIFICATIONS PAGES BRUNSWICK UNIT NO.1 ADMINISTRATIVE AND ORGANIZATIONAL CHANGES
/
(85 TSB 20) i
-l w
8704060297 870401 PDR ADOCK 05000324 (3403NLU/l ah )
P PDR
...-,_..-,..._7,_,,.......
l
SUMMARY
LIST OF REVISIONS BRUNSWICK UNIT NO.1 P_ age Description of Change 3/4 3-51 Table 3.3.5.3-1, Item 2 - Revise B21-LITS-N026A, B to B21-LT-N026A, B 3/4 3-52 Table 3.3.5.3-1, Item 9 - Revise CAC-X-XY-4348-2; to X-XY-4348-2; CAC-X-XY-4349-2; to X-XY-4349-2; CAC-X-XY-4362-2; to X-XY-4362-2; CAC-X-XY-4363-2; to X-XY-4363-2; Table 3.3.5.3-1, Item 10 - Revise CAC-X-XY-4348-1; to X-XY-4348-1; CAC-X-XY-4349-1; to X-XY-4349-1; CAC-X-XY-4362-1; to X-XY-4362-1; CAC-X-XY-4363-1; to X-XY-4363-1; 3/4 3-52a Change footnote designation # to (c) and move footnote to below footnote (b) 3/4 3-52c Table 4.3.5.3-1, Item 2 - Revise B21-LITS-N026A, B to B21-LT-N026A, B Table 4.3.5.3-1, Item 9 - Revise CAC-X-XY-4348-2; to X-XY-4348-2; CAC-X-XY-4349-2; to X-XY-4349-2; CAC-X-XY-4362-2; to X-XY-4362-2; CAC-X-XY-4363-2; to X-XY-4363-2; 3/4 3-52d Table 4.3.5.3-1, Item 10 - Revise CAC-X-XY-4348-1; to X-XY-4348-1; CAC-X-XY-4349-1; to X-XY-4349-1; CAC-X-XY-4362-i; to X-XY-4362-1; CAC-X-XY-4363-1; tp X-XY-4363-1; Change footnote designations
- to (a) and # to (b)
B3/4 5-4 Bases 3/4.5.3.3 - Revise section number 3/4.5.3.3 to 3/4.5.4 j
Change CONDITIONS to OPERATIONAL CONDITIONS Correct misspellir.g of or to on 6-1 Section 6.2.2, Item d. and f. - Change footnote designation
- to (a)
(3403NLU/lah)
SUMMARY
LIST OF REVISIONS (CONT'D)
BRUNSWICK UNIT NO.1 Page Description of Change 6-3 Figure 6.2.1 Revise organizational chart as follows:
Executive Vice President - Power Supply and Engineering &
Construction changed to Senior Executive Vice President - Power Supply and Engineering & Construction Vice President - Corporate Nuclear Safety & Research changed to Manager - Nuclear Safety & Environmental Services. Also, show Manager reporting to Senior Vice President - Operations Support instead of Executive Vice President - Power Supply,and Engineering & Construction Manager - Corporate Nuclear Safety Section changed to Manager - Nuclear Safety Section Manager - Environmental Services Section (reporting to Manager - Nuclear Safety & Environmental Services) should be added Manager - Emergency Prep; redness added to report.to Manager -
Nuclear Safety & Environmental Services Manager - Corporate Health Physics (reporting to Vice President - Corporate Nuclear Safety & Research) should be changed to report to Vice President - Operations Training &
Technical Services Manager - Nuclear Fuels (reporting to Vice President -
Operations Training & Technical Support) should be added Manager - QA/QC Brunswick and Robinson changed to Manager -
QA/QC Operations Section Director - Nuclear Training changed to Manager - Training (BSEP) 6-8 Section 6.2.3.3 - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section Sections 6A.1 and 6.4.2 - Revise Director - Training to Manager - Training (BSEP)
J 6-10 Section 6.5.2.9, Item b. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section (3403NLU/l ah )
- ~ -
SUMMARY
LIST OF REVISIONS (CONT'D)
BRUNSWICK UNIT NO.1 Page Description of Change l
6-12 Section 6.5.3.3, Item e.,- f., and k. - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section 6-13 Section 6.5.3.9 - Revise Vice President - Corporate Nuclear Safety and Research to Manager - Nuclear Safety &
Environmental Services Section 6.5.3.10 - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section Section 6.5.4 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section Section 6.5.4.1 - Revise Corporate Nuclear Safety Section (CNSS) of the Corporate Nuclear Safety & Research Department to Nuclear Safety Section (NSS) of the Nuclear Safety & Environmental Services Department s
6-14 Section 6.5.4.3, 6.5.4.5, 6.5.4.8, and 6.5.4.9 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section 6-15 Section 6.5.4.9, Item g. - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section (twice in same paragraph)
Section 6.5.4.11 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section Section 6.5.4.11, Item a. - Revise CNSS to NSS Section 6.5.4.11, Item c. - Revise Executive Vice President -
Power Supply and Engineering and Construction to Senior Executive Vice President - Power Supply and Engineering &
Construction Revise Vice President - Corporate Nuclear Safety & Research to Manager - Nuclear Safety & Environmental Services 6-17 Section 6.5.5.5 - Revise Quality Assurance Service Section to Quality Assurance Services Section Revise Executive Vice President - Power Supply and Engineering and Construction to Senior Executive Vice President - Power Supply and Engineering & Construction Revise Vice President - Corporate Nuclear Safety & Research to Manager - Nuclear Safety & Environmental Services (3403NLU/l ah )
SUMMARY
L5T OF REVISIONS (CONT'D)
BRUNSWICK UNIT NO.1 M
Description of Change 6-18 Sections 6.6.1, item b.; 6.7.1, Item b.; and 6.7.1, Item d. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section 6-27 Section 6'.10.2, item n. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section (3403NLU/1ah)
~.
(BSEP-1-86)
Eg TABLE 3.3.5.3-1 g
ACCIDENT MONITORINC INSTRUMENTATION i
M M
i MINIMW APPLICABLE g
REQUIRED NUMBER CHANNELS OPERATIONAL j
y INSTRUMENT AND INSTRW ENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION
.l
- 1. Reactor Vessel Pressure 2
1, 1, 2 82 (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) l-
- 2. Reactor Vessel Mater Level 2
1 1, 2 82 (B21-LT-N026A,8; B21-LR-R615; B21-LI-R604A,B; B21-LT-NO37; and B21-LTM-NO37-1) 1
- 3. Suppression. chamber Mater Level 2
1.
1, 2 82 (CAC-LT-2601; CAC-LI-2601-1) g y
(CAC-LT-2602; CAC-LR-2602) 4.-Suppression Chamber Mater Temperature 2
1 1, 2 82(b)
(CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1)
P (CAC-TE-4426-15 thru 26; CAC-TY-4426-23 CAC-TR-4426-2)
- 5. Suppression Chamber Atmosphere Temperature 2
1 1, 2 82(b)
(CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
CAC-TR-4426-1(2); C91-P602)
- 6. Dryvell Pressure 2
1 1, 2 82 3
(CAC-PI-4176; CAC-PT-41763 g
CAC-PR-1257-13 and CAC-PT-4175)
E
- 7. Drywell Temperature 2
1 1, 2 82(b)
(CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-1(2); CAC-TR-4426-1(2); C91-P602) y
- 8. Dryve11 Radiation 2
2 1,2,3 81 (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; I
CAC-AR-1262; CAC-AQH-1262-1,2,3) i
(BSEP-1-86) ll TABLE 3.3.5.3-1 (Continued)
E y
ACCIDENT HONITORING INSTRUMENTATION M
HINIMUM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL y
INSTRUMENT AND INSTRUMENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION
- 9. Drywell Oxygen Concentration 2(a) g(a) 1, 2-82^
-l (CAC-AT-4409-37; CAC-AI-4409-40; X-XY-4348-2; X-XY-4349-2; CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; l
X-XY-4362-2; X-XY-4363-2; CAC-AR-4410-41) i if
- 10. Drywell Hydrogen Concentration Analyzer and Monitor 2(a) g(a)-
1, 2 82 l
(CAC-AT-4409-38; CAC-AI-4409-32; e
Y X-XY-4348-1; X-XY-4349-l;
~
CAC-AR-4409-42)
(CAC-AT-4410-38; CAC-AI-4410-32; i
X-XY-4362-1; X-XY-4363-1; CAC-AR-4410-42)
- 11. Drywell Area Radiation Monitors 2
2 1, 2 81 (D22-RM-4195; D22-RI-4195)
(D22-RM-4196; D22-RI-4196)
(D22-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198) 1 8
{
- 12. Safety / Relief Valve Position Indication
'2/ valve 1/ valve 1, 2 82
+
o" Primary - Sonic (B21-FY-4157 thru 4167) a.
,EE b.
Secondary - Temp. (E21-TR-R614, points 1-11) 4 1
4 1
(BSEP-1-86) as TABLE 3.3.5.3-1 (continued)
Hg ACCIDENT MONITORING INSTRUMENTATION s
b MINIMUN APPLICABLE g
REQUIRED NUMBER CHANNELS OPERATIONAL INSTRUMENT AND INSTRUMENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION g
- 13. Turbine Building Ventilation Monitor (c) 1 1
1,2,3 81 (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)
- 14. Off gas Stack Ventilation Monitor (c) 1 1
1,2,3 81 (D12-RE-4573; D12-RE-4574; D12-RR-4599-2; D12-RR-4599-3)
R Y
U ts (a) An OPERABLE instrument channel shall consist of the AT instrument and either the AI instrument or the h
XY-XY-AR instruments.
n S
(b) See also specification 3.6.2.1 for ACTION requirements for the Suppression Pool Temperature Monitoring System Instrumentation.
(c) High range noble gas monitors.
I
(BSEP-1-86)*
+
l TABLE 4.3.5.3-1 y
ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS s
2:
l E
CHANNEL CHANNEL 1
5 INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION 5
M
- 1. Reactor Vessel Pressure M
R E
(B21-PI-R004A,8; C32-LPR-R608; and C32-PT-N005A,B)
E
R l
1 l
(B21-LT-N026A,8; B21-LR-R615; B21-LI-R604A,B; l
l B21-LT-N037; and B21-LTM-NO37-1)
I
- 3. Suppression Chamber Water Level M
R i
(CAC-LT-2601; CAC-LI-2601-1) l (CAC-LT-2602; CAC-LR-2602) 1
- 4. Suppression Chamber Water Temperature D
R (CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1)
(CAC-TE-4426-15 thru 26; CAC-TY-4426-2; CAC-TR-4426-2)
Y
- 5. Suppression Chamber Atmosphere Temperature M
R (CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
w i
CAC-TR-4426-1(2); C91-P602)
I i
j
- 6. Drywell Pressure M
R i
(CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175) i i
!a l
- 7. Drywell Temperature M
R j
(CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-1(2);
'l CAC-TR-4426-1(2); C91-P602) 1
- 8. Drywell Radiation M
R f
(CAC-AR-1260; CAC-AQH-1260-1,2,3; l
g CAC-AR-1261; CAC-AQH-1261-1,2,3; l
g CAC-AR-1262; CAC-AQH-1262-1,2,3) n.
- 9. Drywell Oxygen Concentration M
R
,o (CAC-AT-4409-37; CAC-AI-4409-40; X-XY--4348-2; X-XY-4349-2; CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; X-XY-4362-2; X-XY-4363-2; CAC-AR-4410-41)
}
I
(BSEP-1-86)
TABLE 4.3.5.3-1 (Continurd)
E-j ACCIDENT HONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E
E CHANNEL CHANNEL I
P' INSTRUMENT AND INSTRUMENT NUMBER CHECK CALIBRATION-4
- 10. Drywell Hydrogen Concentration Analyzer and Monitor M
R y
(CAC-AT-4409-38; CAC-AI-4409-32; X-XY-4348-1; X-XY-4349-1; CAC-AR-4409-42) 4 r.
(CAC-AT-4410-38; CAC-AI-4410-32; X-XY-4362-1; X-XY-4363-1; CAC-AR-4410-42) a R '}
I 11> Drywell Area Radiation Monitor M
(D22-RM-4195; D22-RI-4195)
(D22-RM-4196; D22-RI-4196)
(D22-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198)
- 12. Safety Relief Valve Position Indication a.
Primary - Sonic (B21-FY-4157 thru 4167)
M R
j ti b.
Secondary - Temp. (B21-TR-R614, points 1-11)
M R
- 13. Turbine Building Ventilation Monitor (b)
M R
(D12-RE-4561; D12-RE-4562; A-D12-RR-4548-2; D12-RR-4548-3)
- 14. Off gas Stack Ventilation Monitor (b)
M R
(D12-RE-4573; D12-RE-4574; D12-RR-4599-2; D12-RR-4599-3) 1 i
(a) CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the l
detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr
-]I with an installed or portable gamma source.
y (b) High range noble gas monitors.
l g.
8 4
g:
i i
(BSEP-1-86)
BASES 3/4.5.4 SUPPRESSION POOL l
The OPERABILITY of the suppression pool in OPERATIONAL CONDITIONS 1, 2, or 3 l
is required by Specification 3.6.2.2.
The suppression pool, as part of the ECCS, ensures that a sufficient supply of water is available in the event of a LOCA. This limit on suppression pool minimum water volume ensures that l
sufficient water is available to permit recirculation cooling flow to the Core.
The technical specifications for cooling the reactor core do not make allowances for repair work that might require making the suppression pool i
inoperable unless all irradiated fuel is removed. This specification will permit those repairs to be made and at the same time give assurance that the
. irradiated fuel has an adequate cooling water supply when the suppression pool must be made inoperable, including draining.
1 i
4 I
l I
i l
BRUNSWICK - UNIT 1 B 3/4 5-4 Amendment No.
g (B EE-1-Sb) 6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The General Manager - Brunswick Plant shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1-1.
FACILITY STAFF 6.2.2 The facility organization shall be as shown on Figures 6.2.2-1 and 6.2.2-2 and:
4 a.
Each facility on duty shift shall be composed of at least the minimum facility shift crew composition shown in Table 6.2.2-1.
b.
At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor.
5 When eithar reactor is in OPERATIONAL CONDITION 1, 2, or 3, at least c.
i one licensed Senior Reactor,0perator shall be in the control room.
i Anindividualqualifiedtoimplementradiationgagtectionprocedures i
d.
e I
shall be onsite when fuel is in either reactor.
i a
All CORE ALTERATIONS shall be directly supervised by either a e.
licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilities during.
this operation.
A Fire Brigaje of at least five members shall be maintained onsite at l 2
E.-
all times.
The Fire Brigade shall not: include the minimum shift crew shown in Table 6.2.2-1 or any personnel required ~for.other essential functions during a fire emergency.
4 i
4 a
1 (a) The individual qualified to implement radiation protection procedures and l
Fire Brigade composition may be less than the minimum requirements for a period of time not to exceed two hours in order to accommodate unexpected absence provided immediate action is taken to fill the required postions.
BRUNSWICK - UNIT 1 6-1 Amendment No.
4S
- em Mt" er m.8 4
4 e.=
=
ee.
w em
.6 9
- = -= **
I j
h!
i 1
]I
- h. i t
ai 3i j
_5________.______.
t g
l 4
- 3; ae 35 E
l5 5@
i T
If.
g_
a
-1 g
7__.
i ai I
p 4*
at l
i i
i i
J
~
l r-
T-0 I
i.l li IF I
g I
g g
II l
g h
~
-I l
l.
l
.4 1
lll g
q 15
_a q
- Ri t__.
g t
(BSEP-1-86)
ADMINISTRATIVE CONTROLS 6.2.3 ONSITE NUCLEAR SAFETY (ONS)
FUNCTION 6.2.3.1 The ONS Unit shall function to examine facility operating characterisitics, NRC issues, industry advisories, and other sources which may
)
indicate areas for improving facility safety.
RESPONSIBILITIES 6.2.3.2 The ONS Unit shall be responsible for maintaining surveillance of facility activities to provide independent verification
- that these activities i
are performed correctly and that human errors are reduced as much as practical.
AUTHORITY 6.2.3.3 The ONS Unit shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving facility safety to the Manager - Nuclear Safety Section.
6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Operating Supervisor on matters pertaining to the engineering aspects assuring safe operation of the unit.
6.3 FACILITY STAFF QUALIFICATION 6.3.1 Each member of the facility staff defined in Figure 6.2.2-1 shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Manager - Environmental & Radiation Control who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant during transients and accidents.
j l
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager - Training (BSEP) and l
shall meet or exceed the requirements and recommendations of Section 5.5 of l
ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager - Training (BSEP) and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
- Not responsible for sign-off function.
BRUNSWICK - UNIT 1 6-8 Amendment No.
~.-J 6
o 4
7-~
u
=
4 (BSEP-1-86)
ADMINISTRATIVE CONTROLS 1
i PROCEDURES, TESTS, AND EXPERIMENTS 6.5.2.4 The safety evaluation prepared in accordance with Specifications 6.5.2.1.a and 6.5.2.1.b above shall include a written determination, with basis, of whether or not the procedures, proposed tests i
and experiments, and changes thereto constitute an unreviewed safety question as defined in 10 CFR 50.59, or whether they involve a change to the Technical Specifications.
6.5.2.5 Following the nuclear safety review, the procedures required by 1
Specification 6.8, other procedures that affect nuclear safety, proposed tests or experiments, and changes thereto (other than editorial or typographical) which have been determined to not involve an unreviewed safety question as
}
defined in 10 CFR 50.59 or change to the Technical Specifications shall be J.
approved prior to implementation by the General Manager - Brunswick Plant or his previously designated alternate.
MODIFICATIONS 6.5.2.6 The safety evaluation prepared in accordance with Specificati'n 6.5.2.1.c above shall include a written determination, with basis, of whether or not the proposed modification is a change in the facility as described in the safety analysis report, involves a change to the Technical Specifications, or constitutes an unreviewed safety question as defined in
~
i 10 CFR 50.59.
6.5.2.7 Following the nuclear safety review, proposed modifications which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications shall be approved by the General Manager - Brunswick Plant or his previously designated alternate.
OPERATING LICENSE / TECHNICAL SPECIFICATIONS i
6.5.2.8 The safety evaluation prepared in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above shall include a written i
preliminary determination, with basis, of whether or not the proposed Operating License / Technical Specification change (s) is a change in the facility as described in the safety analysis report.
j 6.5.2.9 Following the nuclear safety review of the safety evaluation prepared in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above and the associated proposed action, the request shall be:
4 Reviewed by the Plant Nuclear Safety Committee in accordance with a.
Specification 6.5.3.8.
b.
Reviewed by the Nuclear Safety Section in accordance with l
Specification 6.5.4.9.
I 4
3 BRUNSWICK - UNIT 1 6-10 Amendment No.
i i
~
w1,-r e -rw r-e
-a-n
-p
-g--. -,- -~ ~
v.+m-,-,
,-s
.,,.w-n--,-----,w,
,,w.-
g,w e--,,,,nwp,e.--g-...e,w e-,--e,e.ww,r w e,wer,s.- en-w
~
(BSEP-1-86)
ADMINISTRATIVE CONTROLS
~
ACTIVITIES 1
6.5.3.8 The PNSC activities shall include the following:
i a.
Review of all procedures required by Specification 6.8 and changes l.
thereto (and any other procedures and changes thereto), any of which j-constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
b.
Review of
'l proposed tests or experiments that constitute an unreviewea safety question or involve a change to the Technical Specifications, prior to implementation.
I a
c.
Review of all proposed modifications that constitute an unrevieced safety question or involve a change to the Technical Specifications, i
prior to implementation.
i i
d.
Review of all proposed changes to the Technical Specifications or l
)
Operating License, prior to implementation.
i e.
Review of reports on violations of Technical Specifications including i
reports covering evaluation and recommendations to prevent recurrence l
to the Vice President - Brunswick Nuclear Project and to the 1
Manager - Nuclear Safety Section.
l f.
Performance of special reviews, investigations (or" analyses), and reports thereon as requested by the Manager - Nuclear Safety Section.
l l
3 Review of all REPORTABLE EVENTS.
1 I
h.
Review of facility operations to detect potential nuclear safety hazards.
i.
Annual review of the Security Plan.
I i
j.
Annual review of the Emergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release 1
including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice
? resident - Brunswick Nuclear Project and the Manager - Nuclear l
Safety Section.
l.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE l
CALCULATION MANUAL.
1 I,
i 1
BRUNSWICK - UNIT 1 6-12 Amendment No.
(~
~
(BSEP-1-86)
ADMINISTRATIVE CONTROLS f
AUTHORITY 6.5.3.9 If there is a disagreement between recommendations of a majority of the j
PNSC and the actions contemplated by the General Manager - Brunswick Plant, the PNSC shall provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -
Brunswick Nuclear Project and the Manager - Nuclear Safety & Environmental Services. The course determined by the Gener:1 Manager - Brunswick Plant to be t
the most conservative shall be followed.
I RECORDS 6.5.3.10 The PNSC shall maintain written minutes of each PNSC meeting that, at a 1
minimum, document the results of all PNSC activities performed under the i
provisions of these Technical Specifications. Copies shall be provided to the Vice President - Brunswick Nuclear Project and the Manager'- Nuclear Safety l
Section.
I 1
6.5.4 NUCLEAR SAFETY SECTION l
FUNCTION i
6.5.4.1 The Nuclear Safety Section (NSS) of the Nuclear Safety & Environmental l
j Services Department shall function to provide independent review of significant j
plant changes, tests, and procedures; verify that REPORTABLE EVENTS are investigated in a timely manner and corrected in a manner that reduces the probability of recurrence of such events; and detect trends that may not be apparent to a day-to-day observer.
i ORGANIZATION 4
6.5.4.2 The individuals assigned responsibility for independent reviews shall be i
specified in technical disciplines. These individuals shall collectively have the experience and competence required to review activities in the following areas:
l j
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy e.
non-destructive testing l
f.
instrumenta' tion and control g.
radiological safety i
h.
mechanical and electrical engineering 3
i.
administrative controls BRUNSWICK - UNIT 1 6-13 Amendment No.
--,..,I
~v
,mm-.v,--y,_,-,
.._m.
_ _,..., _,, _. _ _, _, _,,,,,,,.. ~
,,,-,,.,-..-..-....m.
-%..w.
m.,.,y,
(BSEP-1-86)
ADMINISTRATIVE CONTROLS ORGANIZATION.(Continued) 1 j.
seismic and environmental i
k.
quality assurance practices 1.
Other appropriate fields associated with the unique characteristics i
of the nuclear power plant.
j 6.5.4.3 The Manager - Nuclear Safety Section shall have an academic degree in I_
an engineering or related field and, in addition, shall have a minimum of ten j
years related experience, of which a minimum of five years shall be in the operation and/or design of nuclear power plants.
6.5.4.4 The independent safety review program reviewers shall have an academic degree in an engineering or.related field or equivalent and, in addition, shall have a minimum of five years related experience.-
i 6.5.4.5 An individual may possess. competence in more than one specialty j
area. If sufficient expertise is not available within the Nuclear Safety 1
Section, competent individuals from other Carolina Power & Light Company.
organizations or outside consultants shall be utilized in performing tndependent reviews and investigations.
I 6.5.4.6 At least three individuals, qualified as discussed in 6.5.4.4 above, shall review each item submitted under the requirements of.Section 6.5.4.9.
i
]
6.5.4.7 Independent safety reviews shall be performed by individuals not j
directly involved with the activity under review or responsible for the j
activity under review.
6.5.4.8 The Nuclear Safety Section independent safety review program shall be conducted in accordance with written, approved procedures.
4 t
REVIEW i
l 6.5.4.9 The Nuclear Safety Section shall perform reviews of the following:
l s
The safety evaluations for 1) changes to procedures required by a.
Specification 6.8, 2) modifications of equipment or systems, and L
- 3) tests or experiments that constitute a change to the safety j
analysis report to verify that such actions did not constitute an unreviewed safety question or involve a change to the Technical
{
Specifications.
Implementation may proceed prior to completion of this review.
b.
Proposed changes to procedures required by Specification 6.8, and proposed modifications that constitute an unreviewed safety question l
as defined in 10 CFR 50.59 or a change to the Technical l
Specifications, prior to implementation.
l l
i i
BRUNSWICK - UNIT 1 6-14 Amendment No.
4 1
4 1
___.,,.,.,....,._.,_,_-,,,_,_..,,,,,,.y,,,m,,_.,__.
,,,,_,.,.__.,.,.,_,..,.__,-m,,,._,....,._.__,_.m.,.,,
. ~..... -.. ~.... _
i (BSEP-1-86)
ADMINISTRATIVE CONTROLS a
REVIEW (Continued) c.
Proposed tests or experiments that iuvalve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to implementation.
d.
Proposed changes to the Technical Spt.cifications and Operating License.
e.
Violations, deviations, and events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission, such as:
1.
Violations of applicable codes, regulations, orders, Technical i
Specifications, license requirements, and internal procedures or instructions having nuclear safety significance.
i 2.
Significant operating abnormalities or deviations from normal l
and expected performance of plant safety-related structures, systems, or components.
I f.
Reports and minutes of the PNSC.
f 3
Any other matter involvin6 safe operation of the nuclear power plant that the Manager - Nuclear Safety Section deems appropriate for j
consideration or which is referred to the Manager - Nuclear Safety Section by the on-site operating organization or other functional organisational units within Carolina Power & Light Company.
6.5.4.10 Review of items considered under 6.5.4.9(e) through (g) above shall include the results of any investigations made and the recommendations l
resulting from these investigations to prevent or reduce the probability of l
recurrence of the event.
l RECORDS 6.5.4.11 Records of Nuclear Safety Section reviews, including recommendations l
and concerns, ahall be prepared and distributed as indicated below:
I a.
Copies of documented reviews shall be retained in the NSS files.
l I
b.
hecommendations and concerns shall be submitted to the Ceneral Manager - Brunswick Plant and Vice President - Brunswick Nuclear Project, within 14 days of completion of the review.
c.
A summation of Nuclear Safety recommendations and concerns shall be j
submitted to the Chairman / President and Chief Executive Officert Senior Executive Vice President - Power Supply and Engineering &
i i
Construction; Manager - Nuclear Safety & Environmental Servicess Vice President - Brunswick Nuclear Projects Ceneral Manager - Brunswick
(
Plants and others, appropriate, at least once every two months.
l i
I.
BRUNfWICK - UNIT 1 6-15 Amendment No.
1
-e
.e w.,
--m.---,e.-,--
c
,..w-,--,--mw,
.,-,,-,.-,3--,
,u.,
p-.-,,
..m,.,
,,,,g.m..---.,m-,,.%.we, n.
, n
-m%+,.
.~
~.,.. -....
i (BSEP-1-86) 1-ADMINISTRATIVE CONTROLS AUDITS (Continued) j k.
The performance of activities required by the Quality Assurance I
Program to meet the provisions of Regulatory Cuide 1.21, Revision 1, June 1974, and Regulatory Guide 4.1, Revision 1, April 1975, at least i
once per 12 months.
1.
Any other area of facility operation considered appropriate by the Manager - Quality Assurance Services Section.
6.5.5.3 Personnel performing the quality assurance audits shall have access to the plant operating records.
RECORDS 6.5.5.4 Records of audits shall be prepared and retained.
6.5.5.5 Audit reports. encompassed by 6.5.5.2 above shall be prepared, approved by the Manager - Quality Assurance Services Section, and forwarded to i
the Senior Executive Vice President - Power Supply and Engineering &
Construction; Vice President - Brunswick Nuclear Project; Manager - Nuclear Safety & Environmental Services; Ceneral Manager - Brunswick Plant; and 4
others, as appropriate, within 30 days after completion of the audit.
i l
1 AUTHORITY l
6.5.5.6 The Manager - Quality Assurance Services Section under the Manager -
Corporate Quality Assurance shall be responsible for the following:
a.
The administering of the Corporate Quality Assurance Audit Program.
s b.
The appretral of the individual (s) selected to conduct quality assurance audits.
1 PERSONNEL i
6.5.5.7 Audit personnel shall be independent of the area audited.
2 1
6.5.5.8 Selection of personnel for auditing assignments shall be based on experience or training that establishes that their qualifications are commensurate with the complexity or special nature of the activities to be audited. In selecting audit personnel, consideration shall be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and education.
6.5.5.9 Qualified outside consultants or other individuals independent from those personnel directly involved in plant operation shall be used to augment the audit teams when necessary.
1
)
i l
BRUNSWICK - UNIT 1 6-17 Amendment No.
I l
(BSEP-1-86)
AEMINISTRATIVE CONTROLS 6.546 OUTSIDE AGENCY IllSPECTION AND AUDIT PROGRAM s
J 6.5.6.1 lui independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
6.5.6.2 An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified-fire consultant at intervals no greater than 36 monthe.
1 6.6 REPORTABLE EVENT ACTION
)
6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the Plant Nuclear Safety Committee - Brunswick Plant and shall be submitted'to the Manager -
Nuclear Safety Section and the Vice President - Brunswick Nuclear Project.
6.7 SAFETY LIMIT VIOLATION I
6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
I a.
The facility shall be placed in at least HOT SHUTDOWN within two hours.
b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President -
Brunswick Nuclear Project and the Manager - Nuclear Safety Section l
shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l c.
A Safety Limit Violation Report shall be prepared. The report shall l
be reviewed by the General Manager - Brunswick Plant.. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems, or j
structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the Vice President - Brunswick Nuclear Project, and the i
Manager - Nuclear Safety Section within 14 days of the violation.
)
i 1
I I
1 BRUNSWICK - UNIT 1 6-18 Amendment No.
4 y-g-y,mey y7,
.*w.y, y
-.y.w..,q r
m.,
~,e 7
m....,,.,_.,,
y
%-y,p,,
m-.
.-,.,-.-y.--
..,3.g,_-g,
,,,q
,,p,,-.,,_,9-.
g---,,me,gyg e s
(BSEP-1-86)
ADMINISTRATIVE CONTROLS RECORDS RETENTION (Continued) k.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
L.
Records of the service lives of all hydraulic and mechanical snubbers referenced in Section 3.7.5 including the data at which the service life commences and associated installation and maintenance records.
m.
Records of analyses required by the radiological environmental monitoring program.
Records of (1) meetings of the PNSC, (2) meetings of the previous n.
off-site review organization, the Company Nuclear Safety Committee (CNSC), (3) the independent reviews performed by the Nuclear Safety Section, and (4) the independent reviews performed by the Corporate Quality Assurance Audit Program, Performance ~ Evaluation Unit.
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HICH RADIATION AREA 6.12.1 In lieu of the " Control Device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 meem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the 1
l
' radiation dose rate in the area and alarms when a. preset integrated I
dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
BRUNSWICK - UNIT 1 6-27 Amendment No.
)
i I
ENCLOSURE 2 TO NLS-87-066 PROPOSED TECHNICAL SPECIFICATIONS PAGES BRUNSWICK UNIT NO. 2 ADMINISTRATIVE AND ORGANIZATIONAL CHANGES
\\
(85 TSB 20)
(3403NLU/Iah)
SUMMARY
LIST OF REVISIONS BRUNSWICK UNIT NO. 2 Page Description of Change 3/4 3-51 Table 3.3.5.3-1, Item 2 - Revise B21-LITS-N026A,B to B21-LT-N026A,B 3/4 3-52 Table 3.3.5.3-1, Item 9 - Revise CAC-X-XY-4348-2; to X-XY-4348-2; CAC-X-XY-4349-2; to X-XY-4349-2; CAC-X-XY-4362-2; to X-XY-4362-2; CAC-X-XY-4363-2; to X-XY-4363-2; Table 3.3.5.3-1, Item 10 - Revise CAC-X-XY-4348-1; to X-XY-4348-1; CAC-X-XY-4349-1; to X-XY-4349-1; CAC-X-XY-4362-1; to X-XY-4362-1; CAC-X-XY-4363-1; to X-XY-4363-1; 3/4 3-52a Change footnote designation # to (c) and move footnote to below footnote (b) 3/4 3-52c Table 4.3.5.3-1, Item 2 - Revise B21-LITS-N026A,B to B21-LT-N026A,B Table 4.3.5.3-1. Item 9 - Revise CAC-X-XY-4348-2; to X-XY-4348-2; CAC-X-XY-4349-2; to X-XY-4349-2; CAC-X-XY-4362-2; to X-XY-4362-2; CAC-X-XY-4363-2; to X-XY-4363-2; 3/4 3-52d Table 4.3.5.3-1, Item 10 - Revise CAC-X-XY-4348-1; to X-XY-4348-1; CAC-X-XY-4349-1; to X-XY-4349-1; CAC-X-XY-4362-1; to X-XY-4362-1; CAC-X-XY-4363-1; to X-XY-4363-1; Change footnote designations
- to (a) and # to (b) 3/4 3-57 Table 3.3.5.6-2, Item 2b. - Revise narrow range monitor (TS-CR-B63) to narrow range monitor (TS-CR-863)
B3/4 5-4 Bases 3/4.5.3.3 - Revise section number 3/4.5.3.3 to 3/4.5.4 Change CONDITIONS to OPERATIONAL CONDITIONS Correct misspelling of or to on (3403NLU/lah)
7
SUMMARY
LIST OF REVISIONS (CONT'D)_
BRUNSWICK UNIT NO. 2 P_ age Description of Change a
6-1 Section 6.2.2, item d. and f. - Change footnote designation
- to (a) 6-3 Figure 6.2.1 Revise organizational chart as follows:
Executive Vice President - Power Supply and Engineering &
Construction changed to Senior Executive Vice President - Power Supply and Engineering & Construction Vice President - Corporate Nuclear Safety & Research changed to Manager - Nuclear Safety & Environmental Services. Also, show Manager reporting to Senior Vice President - Operations Support instead of Executive Vice President - Power Supply and Engineering & Construction il
}
Manager - Corporate Nuclear Safety Section changed to Manager - Nuclear Safety Section L
i Manager - Environmental Services Section (reporting to Manager - Nuclear Safety & Environmental Services) should be added~
Manager - Emergency Preparedness added to report to Manager -
Nuclear Safety & Environmental Services Manager - Corporate Health Physics (reporting to Vice President - Corporate Nuclear Safety & Research) should be changed to report to Vice President - Operations Training &
j Technical Services Manager - Nuclear Fuels (reporting to Vice President -
Operations Training & Technical Support) should be added i
Manager - QA/QC Brunswick and Robinson changed to Manager -
QA/QC Operations Section Director - Nuclear Training changed to Manager - Training (BSEP) i 6-8 Section 6.2.3.3 - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section f
Sections 6.4.1 and 6.4.2 - Revise Director - Training to Manager - Training (BSEP) 6-10 Section 6.5.2.9, item b. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section 1
(3403NLU/lah )
i i
~
SUMMARY
LIST OF REVISIONS (CONT'D)
BRUNSWICK UNIT NO. 2 Page Description of Change 6-12 Section 6.5.3.8, Item e., f., and k. - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section 6-13 Section 6.5.3.9 - Revise Vice President - Corporate Nuclear Safety and Research to Manager - Nuclear Safety &
Environmental Services Section 6.5.3.10 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section Section 6.5.4 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section Section 6.5.4.1 - Revise Corporate Nuclear Safety Section (CNSS) of the Corporate Nuclear Safety & Research Department to Nuclear Safety Section (NSS) of the Nuclear Safety & Environmental Services Department 6-14 Sections 6.5.4.3, 6.5.4.5, 6.5.4.8, and 6.5.4.9 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section 6-15 Section 6.5.4.9, Item g. - Revise Manager - Corporate Nuclear Safety Section to Manager - Nuclear Safety Section (twice in same paragraph)
Section 6.5.4.11 - Revise Corporate Nuclear Safety Section to Nuclear Safety Section Section 6.5.4.11, Item a. - Revise CNSS to NSS Section 6.5.4.11, item c. - Revise Executive Vice President -
Power Supply and Engineering and Construction to Senior Executive Vice President - Power Supply and Engineering &
Construction j
Revise Vice President - Corporate Nuclear Safety & Research to Manager - Nuclear Safety & Environmental Services 6-17 Section 6.5.5.5 - Revise Quality Assurance Service Section to Quality Assurance Services Section i
j Revise Executive Vice President - Power Supply and Engineering and Construction to Senior Executive Vice President - Power i'
Supply and Engineering & Construction Revise Vice President - Corporate Nuclear Safety & Research to Manager - Nuclear Safety & Environmental Services (3403NLU/Ish )
SUMMARY
LIST OF REVISIONS (CONT'D)
BRUNSWICK UNIT NO. 2 P_ajte Description of Change 6-18 Sections 6.6.1, Item b.; 6.7.1, Item b.; and 6.7.1, Item d. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section 6-27 Section 6.10.2, item n. - Revise Corporate Nuclear Safety Section to Nuclear Safety Section i
\\
)
I 1
l 4
l t
l (3403NLU/lah)
(BSEP-2-88)
'E TABLE 3.3.5.3-1
,E ACCIDENT MONITORINC INSTRUMENTATION 5
1 n*
MINIMtM APPLICABLE REQUIRED NUMBER CHANNELS OPERATIONAL z
INSTRUMENT Alm INSTRLBfENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION
- 4 w
- 1. Reactor Vessel Pressure 2
1 1, 2 82 (B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,5) l
1 1, 2 82 (B21-LT-N026A,B; B21-LR-R615; 821-LI-R604A,B; B21-LT-N037; e.nd 821-LTM-N037-1)
- 3. Suppression Chamber Water 14 vel 2
1 1, 2 82 (CAC-LT-2601; CAC-LI-2601-1)
(CAC-LT-2602; CAC-LR-2602) y
- 4. Suppression Chamber Water Temperature 2
1 1, 2 82(b) p (CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1)
(CAC-TE-4426-15 thru 26; CAC-TY-4426-2; CAC-TR-4426-2)
- 5. Suppression Chamber Atmosphere Temperature 2
1.
1, 2 82(b)
(CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
CAC-TR-4426-1(2); C91-P602)
- 6. Drywell Pressure 2
1 1, 2 82 (CAC-PI-4176; CAC-PT-4176; g
CAC-PR-1257-1; and CAC-PT-4175)
E
- 7. Drywell Temperature 2
1 1, 2 82(b)
(CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-1(2); CAC-TR-4426-1(2); C91-P602)
- 8. Drywell Radiation 2
2 1,2,3 81 (CAC-AR-1260; CAC-AQH-1260-1,2,3; CAC-AR-1261; CAC-AQH-1261-1,2,3; CAC-AR-1262; CAC-AQH-1262-1,2,3)
(BSEP-2-88)
E TABLE 3.3.5.3-1 (Continued)
E s
E ACCIDENT MONITORINC INSTRUMENTATION R
r:
MINIMUM APPLICABLE l
E REQUIRED NUMBER CHANNELS OPERATIONAL Q
INSTRUMENT AND INSTRIMENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION u
2 *)
1(a) 1, 2 82 I
- 9. Drywell Oxygen Concentration (CAC-AT-4409-37; CAC-AI-4409-40; g
X-XY-4348-2; X-XY-4349-2; e
l CAC-AR-4409-41) i (CAC-AT-4410-37; CAC-AI-4410-40; l
X-XY-4362-2; X-XY-4363-2; CAC-AR-4410-41) u 2 *)
I I *)
1, 2 82 I
- 10. Dryve11 Hydrogen Concentration Analyzer and Monitor Y
(CAC-AT-4409-38; CAC-AI-4409-32; g.
U X-XY-4348-1; X-XY-4349-1; CAC-AR-4409-42 )
1 (CAC-AT-4410-38; CAC-AI-4410-32; l-X-XY-4362-1; X-XY-4363-1; a
I CAC-AR-4410-42) 1
- 11. Drywell Area Radiation Mon,itors 2
2 1, 2 81 (D22-RM-4195; D22-RI-4195)
(D22-RM-4196; D22-RI-4196)
(D22-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198)
F j
'[
- 12. Safety / Relief Valve Position Indication 2/ valve 1/ valve 1, 2 82 p$
Primary - Sonic (821-FY-4157 thru 4167) a.
j b.
Secondary - Temp. (B21-TR-R614, points 1-11) i U
i l
i 1
i
~
(BSEP-2-88)
~
h TABLE 3.3.5.3-1 (Continued)
N Q
ACCIDENT MONITORINC INSTRUMENTATION B
h MINIMUM APPLICABLE "8
REQUIRED NUMBER CHANNELS OPERATIONAL INSTRUMENT AND INSTRIMENT NUMBER OF CHANNELS OPERABLE CONDITIONS ACTION
- 13. Turbir.e Building Ventilation Monitor (c) 1 1
1,2,3 81 (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3) i
- 14. Off gas Stack Ventilation Monitor (c) 1 1
1,2,3 81 l
(D12-RE-4573; D12-RE-4574; D12-RR-4599-2; D12-RR-4599-3) k s-Y U
o (a) An OPERABLE instrument channel shall consist of the AT instrument and either the AI instrument or the XY-XY-AR instruments.
i l
(b) See also specification 3.6.2.1 for ACTION requirements for the Suppression Pool Temperature Monitoring l
System Instrumentation.
s l
(c) High range noble gas monitors.
l l
u
l (BSEP-2-88 )
TABLE 4.3.5.3-1 l
ACCIDENT MONITORINC INSTRIMENTATION SURVEILIANCE REQUIREMENTS z
E CHANNEL CHANNEL N
INSTRUMENT AND INSTRIMENT NUMBER CHECK CALIBRATION 7:
- 1. Reactor Vessel Pressure M
R E
(B21-PI-R004A,B; C32-LPR-R608; and C32-PT-N005A,B) e u
R l
-(B21-LT-N026A,5; B21-LR-R615; B21-LI-R604A,B; l
821-LT-NO37; and B21-LTM-NO37-1)
- 3. Suppression Chamber Water Level M
R (CAC-LT-2601; CAC-LI-2601-1)
(CAC-LT-2602; CAC-LR-2602)
- 4. Suppression Chamber Water Temperature D
R Q
(CAC-TE-4426-2 thru 13; CAC-TY-4426-1; CAC-TR-4426-1)
(CAC-TE-4426-15 thru 26; CAC-TY-4426-2; CAC-TR-4426-2)
Y$
- 5. Suppression Chamber Atmosphere Temperature M
R (CAC-TE-1258-17 thru 20; CAC-TY-4426-1(2);
o CAC-TR-4426-1(2); C91-P602)
- 6. Drywell Pressure M
R (CAC-PI-4176; CAC-PT-4176; CAC-PR-1257-1; and CAC-PT-4175)
- 7. Drywell Temperature M
R l
(CAC-TE-1258-1 thru 13, 22, 23, 24; CAC-TY-4426-1(2);
l CAC-TR-4426-1(2); C91-P602) 1
- 8. Drywell Radiation M
R f
(CAC-AR-1260; CAC-AQH-1260-1,2,3; E
CAC-AR-1261; CAC-AQH-1261-1,2,3; g
CAC-AR-1262; CAC-AQH-1262-1,2,3)
N
- 9. Dryvell OxyRen Concentration M
R g
0 (CAC-AT-4409-37; CAC-AI-4409-40; I-IY-4348-2; I-IY-4349-2; CAC-AR-4409-41)
(CAC-AT-4410-37; CAC-AI-4410-40; I-IY-4362-2; I-IY-4363-2; CAC-AR-4410-41)
(BSEP-2-88)
TABLE 4.3.5.3-1 (Continued) g ACCIDENT MONITORINC INSTRLMENTATION SURVEILLANCE REQUIREMENTS Ey CHANNEL CHANNEL g
INSTRUMENT AND INSTRIMENT NUMBER CHECK CALIBRATION x
- 10. Dryvell Hydrogen Concentration Analyzer and Monitor M
R 8
g (CAC-AT-4409-38; CAC-AI-4409-32; X-XY-4348-1; y
X-XY-4349-1; CAC-AR-4409-42)
(CAC-AT-4410-38; CAC-AI-4410-32; X-XY-4362-1; X-XY-4363-1; CAC-AR-4410-42)
IR ")
- 11. Drywell Area Radiation Monitor M
(D22-RM-4195; D22-RI-4195)
(D22-RM-41%; D22-RI-4196)
(D22-RM-4197; D22-RI-4197)
(D22-RM-4198; D22-RI-4198) l
- 12. Safety Relief Valve Position Indication Primary - Sonic (B21-FY-4157 thru 4167)
M R
a.
o) b.
Secondary - Temp. (B21-TR-R614, points 1-11)
M R
)
l
[
- 13. Turbine Building Ventilation Monitor (b)
M R
g (D12-RE-4561; D12-RE-4562; D12-RR-4548-2; D12-RR-4548-3)
- 14. Off gas Stack Ventilation Monitor (b) y R
(D12-RE-4573; D12-RE-4574; j
D12-RR-4599-2; D12-RR-4599-3)
(a) CHANNEL CALIBRATION shall consist of an electronic calibration of the channel, not including the detector, for range decades above 10R/hr and a one point calibration check of the detector below 10R/hr f
with an installed or portable gamma source.
g, (b) High range noble gas monitors.
l E
u
.F
~
(BSEP-2-84) i TABLE 3.3.5.6-2 es E
CHLORIDE INTRUSION MONITORS SETPOINTS 5
5 Q
FUNCTIONAL UNIT AND INSTRUMENT NIMBER ALARM SETPOINT ALIAWABLE LIMIT i
l 1.
Chloride leak detectors in the condenser
$ 1.0 pahos/cm
~< 2.0 pahos/cm c
l 5.4 hotwell outlet headers (CO-CR24) 2.
Chloride leak Jetector in the condensate pump discharge a.
Wide range monitor (CO-CIS-3075-1)
$ 2.0 pahos/cm
$ 10 pahos/cm b.
Marrow range monitor (TS-CR-863)
$ 0.3 pahos/cm
$ 0.5 pahos/cm 3.
Chloride leak detector in the inlet to the 3 0.3 pahos/cm
$ 0.5 pahos/cm filter domineralizer (CFD-CIT-1)
R Y.
the deep bed domineralizer (CDD-CIT-1)
-< 0.3 pahos/cm
< 0.5 pahos/cm 4.
Chloride leak Jetector in the inlet to
~
u E
a F.
. r 1.
- _:-..,... c-...
a (BSEP-2-88)
BASES i
3/4.5.4 SUPPRESSION POOL l
4
)
The OPERABILITY of the suppression pool in OPERATIONAL CONDITIONS 1, 2, or 3 l
4 is required by Specification 3.6.2.2.
The suppression pool, as part of the ECCS, ensures that a sufficient supply of water is available in the event of a LOCA. This limit on suppression pool minimum water volume ensures that l
sufficient water is available to permit recirculation cooling flow to the core.
The technical specifications for cooling the reactor core do not make allowances for repair work that might require making the suppression pool inoperable unless all irradiated fuel is removed. This specification will permit those repairs to be made and at the same time give assurance that the irradiated fuel has an adequate cooling water supply when the suppression pool i
must be made inoperable, including draining.
I I
i a
f J
l J
J i
i t
t I
4 4
i i'
BRUNSWICK - UNIT 2 B 3/4 5-4 Amendment No.
i
. - - - - - -. ~. ~,. - _.,.
, - -.. - - - - -... - - -.. l
_.u
.:::'.L:.
- ~....
~ a:
=..
~
(BSEP-2-88) 6.0 ADMINISTRATIVE CONTROLS t
6.1 RESPONSIBILITY l
l 6.1.1 The General Manager - Brunswick Plant shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.
I 6.2 ORGANIZATION OFFSITE l
6.2.1 The offsite organization for facility management and technical support shall be as shown on Figure 6.2.1-1.
FACILITY STAFF
]i 4
6.2.2 The facility organisation shall be as shown on Figures 6.2.2-1 and j
'6.2.2-2 and:
a.
Each facility on duty shift shall be composed of at least the minimum facility shift crew composition shown in Table 6.2.2-1.
I b.
At least one licensed kvactor Operator'shall be in the control room when fuel is in the reactor.
5 When either reactor is in 01ERATIONAL CONDITION 1,. 2, or 3, at least c.
one licensed Senior Reactor Operator shall be in the control room.
An individual qualified to implement radiation g tection procedures l
d.
shall be onsite when fuel is in either reactor.
j e.
All CORE ALTERATIONS shall be directly supervised.by either.a licensed Senior Rasetor Operator or. Senior-Reactor Operator Limited j
to Fuel Handling who has no other concurrent responsibilities during this operation.
l A Fire Brige of at least five members shall be maintained onsite at f.
all times.
The Fire Brigade shall not include the minimum shift crew shown in Table 6.2.2-1 or any personnel required for other essential functions during a fire emergency.
i (a) The individual qualified to implement radiation protection procedures and l
j Fire Brigade composition may be less than the minimum requirements for a i
period of time not to exceed two hours in order to accommodate unexpected 4
absence provided immediate action is taken to fill the required postions.
BRUNSWICK - UNIT 2 6-1 Amendment No.
. ~ -
I H
I a
i i
aj 3
I I
e 4
._____J 5
5j E
59 i
3 gg
..I g
.__.g b
I p
4 st I
i i
c
~~
~~
8 g
l 4
7
_.I ML
- N k
-t i.
I l$
[
II l
5 N
i g
.I
__ g y
8 g!
r,l' I
... - - -. _ ~
i I
(BSEP-2-88) i 1
ADMINISTRATIVE CONTROLS I
j 6.2.3 ONSITE NUCLEAR SAFETY (ONS) i j
FUNCTION 3
i 6.2.3.1 The ONS Unit shall function to examine facility operating j
characterisitics, NRC issues, industry advisories, and other sources which may indicate areas for improving facility safety.
RESPONSIBILITIES
}
}
6.2.3.2 The ONS Unit shall be responsible for maintaining surveillance of facility activities to provide independent verification
- that these activities i
are performed correctly and that human errors are reduced as much as
)
l practical.
4 i
AUTNORITY Ii 6.2.3.3 The ONS Unit shall make detailed recommendations for revised procedures, equipment modifications, or other means of improving facility l
safety to the Manager - Nuclear Safety Section.
6.2.4 SHIFT TECHNICAL ADVISOR l
4 1
6.2.4.1 The Shift Technical Advisor shall serve in an advisory capacity to the Shift Operating Supervisor on matters pertaining to the engineering i
aspects assuring safe operation of the unit.
1
+
6.3 FACILITY STAFF QUALIFICATION 6.3.1 Each member of the faellity staff defined in Figure 6.2.2-1 shall meet j
or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Manager - Environmental & Radiation Control who I
shall meet or exceed the qualifications of Regulatory Culde 1.8, J
September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's i
degree or equivalent in a scientific or engineering discipline with specific I
training in plant design, and response and analysis of the plant during
{
transients and accidents.
6.4 TRAINING l
6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Manager - Training (BSEP) and l
l shall meet or exceed the requirements and recommendations of Section 5.5 of l
ANSI N18.1-1971 and Appendia "A" of 10 CFR Part 55.
1 6.4.2 A training program for the Fire Brigade shall be maintained under the i
direction of the Manager - Training (BSEP) and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975.
l
- Not responsible for sign-off function.
i
}
BRUNSWICK - UNIT 2 6-8 Amendment No.
i
. _ _. _, _ _ _. ~,, _
(BSEP-2-88)
ADMINISTRATIVE CONTROLS PROCEDURES. TESTS, AND EXPERIMENTS 6.5.2.4 The safety evaluation prepared in accordance with Specifications 6.5.2.1.a and 6.5.2.1.b above shall include a written determination, with basis, of whether or not the procedures, proposed tests and experiments, and changes thereto constitute an unreviewed safety question as defined in 10 CFR 50.59, or whether *. hey involve a change to the Technical Specifications.
6.5.2.5 Following the nuclear safety review, the procedures required by Specification 6.8, other procedures that affect nuclear safety, proposed tests or experiments, and changes thereto (other than editorial or typographical) which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or change to the Technical Specifications shall be approved prior to implementation by the General Manager - Brunswick Plant or his previously designated alternate.
MODIFICATIONS 6.5.2.6 The safety evaluation prepared in accordance with Specification 6.5.2.1.c above shall include a written determination, with basis, of whether or not the proposed modification is a change in the facility as described in the safety analysis report, involves a change to the Technical Specifications, or constitutes an unreviewed safety question as defined in 10 CFR 50.59.
6.5.2.7 Following the nuclear safety review, proposed modifications which have been determined to not involve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications shall be approved by the General Manager - Brunswick Plant or his previously designated alternate.
OPERATING LICENSE / TECHNICAL SPECIFICATIONS 6.5.2.8 The safety evaluation prepared in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above shall include a written preliminary determination, with basis, of whether or not the proposed Operating License / Technical Specification change (s) is a change in the facility as described in the safety analysis report.
6.5.2.9 Following the nuclear safety review of the safety evaluation prepared l
in accordance with Specifications 6.5.2.1.d and 6.5.2.1.e above and the associated proposed action, the request shall bet a.
Reviewed by the Plant Nuclear Safety Committee in accordance with Specification 6.5.3.8.
b.
Reviewed by the Nuclear Safety Section in accordance with specification 6.5.4.9.
BRUNSWICK - UNIT 2 6-10 Amendment No.
(BSEP-2-88)
ADMINISTRATIVE CONTROLS ACTIVITIES 6.5.3.8 The PNSC activities shall include the followings a.
Review of all procedures required by Specification 6.8 and changes thereto (and any other procedures and changes thereto), any of which constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
b.
Review of all proposed tests or experiments that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
c.
Review of all proposed modifications that constitute an unreviewed safety question or involve a change to the Technical Specifications, prior to implementation.
d.
Review of all proposed changes to the Technical Specifications or Operating License, prior to implementation.
Review of reports on violations of Technical Specifications including e.
reports covering evaluation and recommendations to prevent recurrence to the Vice President - Brunswick Nuclear Project and to the Manager - Nuclear Safety Section.
f.
Performance of special reviews, investigations (or analyses), and reports thereon as requested by the Manager - Nuclear Safety Section.
g.
Review of all REPORTABLE EVENTS.
h.
Review of facility operations to detect potential nuclear safety hazards.
1.
Annual review of the Security Plan.
J.
Annual review of the Emergency Plan.
k.
Review of accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the Vice President - Brunswick Nuclear Project and the Manager - Nuclear Safety Section.
1.
Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION HANUAL.
BRUNSWICK - UNIT 2 6-12 Amendment No.
(BSEP-2-88) 1 ADMINISTRATIVE CONTROI.S l
AUTHORITY i
6.5.3.9 If there is a disagreement between recommendations of a majority of the PNSC and the actions contemplated by the General Manager - Brunswick Plant, the PNSC shall provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President -
Brunswick Nuclear Project and the Manager - Nuclear Safety & Environmental Services. The course determined by the Ceneral Manager - Brunswick Plant to be i
the most conservative shall be followed.
RECORDS 6.5.3.10 The PNSC shall maintain written minutes of each PNSC meeting that, at a i
minimum, document the results of all PNSC activities performed under the provisions of these Technical Specifications. Copies shaLL be provided to the Vice President - Brunswick Nuclear Project and the Manager - Nuclear Safety l
Section.
l 6.5.4 NUCt. EAR SAFETY SECTION FUNCTION 6.5.4.1 The Nuclear Safety Section (NSS) of the Nuclear Safety & Environmental l
~
l Services Department shall function to provide independent review of significant plant changes, tests, and procedurest verify that REPORTABt.E EVENTS are investigated in a timely manner and corrected in a manner that reduces the probablLity of recurrence of such events; and detect trends that may not be apparent to a day-to-day observer.
ORCANIZATION i
I 6.5.4.2 The individuals assigned responsibility for independent reviews shaLL be l
specified in technical disciplines. These individuals shaLL collectively have the experience and competence required to review activities in the following areast a.
nuclear power plant operations l
b.
nuclear eng(neering I
c.
chemistry and radiochemistry d.
metallurgy e.
non-destructive testing f.
Instrumentation and control s.
radiological safety a
i h.
mechanical and electrical engineering
\\
l L.
administrative controls i
l l
BRUNSWICK - UNIT 2 6-13 Amendment No.
(BSEP-2-88)
ADMINISTRATIVE CONTROLS ORCANIZATION (Continued) j.
seismic and environmental k.
quality assurance practices L.
Other appropriate fields associated with the unique characteristics of the nuclear power plant.
6.5.4.3 The Manager - Nuclear Safety Section shall have an academic degree in l
an engineering or related field and, in addition, shall have a minimum of ten years related experience, of which a minimum of five years shaLL be in the operation and/or design of nuclear power plants.
6.5.4.4 The independent safety review program reviewers shall have an academic degree in an engineering or related field or equivalent and, in addition, shall have a minimum of five years related experience.
6.5.4.5 An individual may possess competence in more than one specialty l
area. If sufficient expertise is not available within the Nuclear Safety l
Section, competent individuals from other Carolina Power & Light Company organizations or outside consultants shall be utilised in performing independent reviews and investigations.
6.5.4.6 At lesst three individuals, qualified as discussed in 6.5.4.4 above, shaLL review each item submitted under the requirements of Section 6.5.4.9.
6.5.4.7 Independent safety reviews shall be performed by individuals not directly involved with the activity under review or responsible for the activity under review.
6.5.4.8 The Nuclear Safety Section independent safety review rcogram shall be l
conducted in accordance with written, approved procedures.
REVIEW 6.5.4.9 The Nuclear Safety Section shall perform reviews of the followingt l
The safety evaluations for 1) changes to procedures required by a.
Specification 6.8, 2) modifications of equipment or systems, and r
- 3) tests or experiments that constitute a change to the safety analysis report to verify that such actions did not constitute an unreviewed safety question or involve a change to the Technical Specifications.
Implementation may proceed prior to completion of this review.
b.
Proposed changes to procedures required by Specification 6.8, and proposed modifications that constitute an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Technical Specifications, prior to implementation.
8RUNSWICK - UNIT 2 6-14 Amendment No.
_ gg,.-
7-
~-__- -.~..-
(BSEP-2+88) j ADMINISTRATIVE CONTROLS 1'
REVIEW (Continued) c.
Proposed tests or esperiments that favolve an unreviewed safety question as defined in 10 CFR 50.59 or a change to the Te.hnical Specifications, prior to implementation.
I 8
d.
Proposed changes to the Technical Specifications and Operating License.
l e.
Violations, deviations, and events requiring 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> written notification to the Commission, such ass i
i 1.
Violations of applicable codes, regulations, orders, Technical i
specifications, license requirements, and internal procedures or j
instructions having nuclear safety significance.
i j
2.
Significant operating abnormalities or deviations from normal j
and espected performance of plant safety-related structures, j
systems, or components.
'j t
f.
Reports and minutes of the PWSC.
3 Any other matter involving safe operation of the nuclear power plant i
that the Manager - Nuclear Safety Section deems appropriate for l
i consideration or which is referred to the Manager - Nuclear Safety I
Section by the on-site operating organisation or other functional organisational units within Carolina Power,4 Light Company.
1 l
j 6.5.4.10 Review of items considered under 6.5.4.9(e) through (3) above shall j
include the results of any investigations made and the recommendations i
j resulting from these investigations to prevent or reduce the probabllity of recurrence of the event.
I RECORDS 6.5.4.11 Records of Nuclear Safety Section reviews, including recommendations l
j and concerns, shall be prepared and distributed as indicated below l
j a.
Copies of documented reviews shall be retained in the NSS flies.
l b.
Recosumendations and concerne shall.be submitted to the General Manager - Brunswick Plant and Vice President - Brunswick Nuclear Project, within 14 days of completion of the review.
c.
A sununation of Nuclear Safety recommendations and concerne shall be i
submitted to the Chairman / President and Chief Esecutive Officert Senior Esecutive Vice President - Power Supply and Engineering & Constructiont l
Manager - Nuclear Safety & Environmental Servicess Vice President -
Brunswick Nuclear Project) General Manager - Brunswick Planti and i
others, appropriate, at least once every two months.
l 1
i
\\
i 1
BRUNSWICK - UNIT 2 6-15 Amendment No.
)
- -, ~ -,, - -.. -. - _. _ - _. _ _ _. - - -. -, -. - - _. -..
--_ ~
(SSEP-2-88) 1 ADMINISTRATIVE CONTROLS
}
AUDITS (Continued) i' k.
The performance of activities required by the quality Assurance i
Program to meet the provisions of Regulatory Culde 1.21, Revision 1, l
June 1974, and Regulatory Guide 4.1, Revision 1, April 1975, at least l
once per 12 months.
i 1.
Any other area of facility operation considered appropriate by the Manager - quality Assurance Services Section.
i 6.5.5.3 Personnel performing the quality assurance audits shall have access j
to the plant operating records.
REcotDS i
l 4.5.5.4 Records of audits shall be prepared and retained.
l 6.5.5.5 Audit reports encompassed by 6.5.5.2 above shall be prepared, approved by the Manager - quality Assurance Services Section, and forwarded to I
the Senior Esecutive Vice President - Power Supply and Engineering &
Constructions Vice President - Stunswick Nuclear Projecti Manager - Nuclear 1
Safety & Environmental Servicess General Manager - Stunswick Planti and others, as appropriate, within 30 days after completion of the audit.
?
AUTHORITY 6.5.5.6 The Manager - Quality Assurance Services Section under the Manager -
Corporate que11ty Assurance 6tatt be responsible for the followingt j
a.
The administering of the Corporate quality Assurance Audit Program.
b.
The approval of the individual (s) selected to conduct qus11ty l
assurance audits.
l PERSONWgL i
4.5.5.7 Audit personnet shall be independent of the area audited.
I i
6.5.5.8 Selection of personnet for auditing assignments shall be based on l
esperience or training that estabilshes that their qualifications are consensurate with the complesity or special nature of the activities to be audited. In selecting audit personnel, consideration shall be given to special abilities, specialised technical training, prior pertinent esperience, personal characteristics, and education.
I i
6.5.5.9 quellfled outside consultants or other individuals independent from those personnel directly involved in plant operation shall be used to augment the audit teams when necessary.
I i
j BauMSWICK - UNIT 2 6-17 Amendment No.
(BSEP-2-88)
I e
ADMINISTRATIVE CONTROLS 6.5.6 OUTSIDE AGENCY INSPECTION AND AUDIT PROCRAM 6.5.6.1 An independent fire protection and loss prevention inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite Licensee personnel or an outside fire protection firm.
6.5.6.2 An inspection and audit of the fire protection and loss prevention program shall be performed by an outside qualified fire consultant at intervals no greater than 36 months.
6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTSt 1
I a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shaLL be reviewed by the Plant Nuclear Safety Committee - Brunswick Plant and shall be submitted to the Manager -
l Nuclear Safety Section and the Vice President - Brunswick Nuclear
)
Project.
1 6.7 SAFETY LIMIT VIOLATION l
6.7.1 The following actions shaLL be taken in the event a safety Limit is i
violatedt a.
The facility shall be placed in at least HOT SHUTDOWN within two j
hours.
i b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour. The Vice President -
g Brunswick Nuclear Project and the Manager - Nuclear Safety Section
[
shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety Limit Violation Report shall be prepared. The report shall
)
c.
be reviewed by the General Manager - Brunswick Plant. This report l
shall describe (1) applicable circumstances preceding the violation,
)
(2) effects of the violation upon facility components, systems, or l
structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the Vice President - Brunswick Nuclear Project, and the Manager - Nuclear Safety Section within 14 days of the vloistion.
i 1
I BRUNSWICK - UNIT 2 6-18 Amendment No.
(BSEP-2-88) o ADMINISTRATIVE CONTROLS RECORDS RETENTION (Continued) k.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
L.
Records of the service lives of all hydraulic and mechanical snubbers referenced in Section 3.7.5 including the data at which the service life commences and associated installation and maintenance records.
m.
Records of analyses etiquired by the radiological environmental monitoring program.
n.
Records of (1) meetings of the PNSC, (2) meetings of the previous off-site review organization, the Company Nuclear Safety Committee (CNSC), (3) the independent reviews performed by the Nuclear Safety Section, and (4) the independent reviews performed by the Corporate Quality Assurance Audit Program, Performance Evaluation Unit.
6.11 RADIATION PROTECTION PROGRAM 6.11.1 Procedures for personnel radiat*on protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HICH RADIATION AREA 6.12.1 In lieu of the " Control Device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem /hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*.
Any Individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followings A radiation monitoring device which continuously indicates the a.
radiation dose rate in the area.
b.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them.
- Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
BRUNSWICK - UNIT 2 6-21 Amendment No.
-