ML20002C420
| ML20002C420 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/08/1976 |
| From: | Bilby C CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20002C417 | List: |
| References | |
| NUDOCS 8101100280 | |
| Download: ML20002C420 (17) | |
Text
._.
(
J :...i.o,, l. ili. >.,bj ! -
CONSUM:RS POWER COMPANY Docket No 50-155
,iLu.)~f.176 L.
Request for Change to the Technical Specifications License No DPR-6 I.
For the reasons hereinafter set forth, the following changes to the Tech-nical Specifications of License No DPR-6 issued to Consumers Power Company on May 1, 196b for the Big Rock Point Plant are requested:
A.
Remove Page 111. " Contents," and replace it with the following:
(
I l
i l
h$dh).$hhb
\\
\\
~~s CONTEN
- ontd)
Page No.
70 Operating Procedures.
7-1 T.1 Deleted.
T.2 Deleted.
7.2.1 Deleted.
7.2.2 Deleted.....
7.2.3 Deleted.
7.2.4 Administrative and Procedural Controls Relating to High Performance Puel T-3 7.3 Normal Operation 7-3 7.3.1 General.
7-3 7.3 2 Cold Start-Up After Extended Shutdown..
7-3 7 3.3 Hot Start-Up 74 7.3.5 Extended Shutdown.
7-5 7.3.6 Short Duration Shutdos, 7-6 7.4 Refueling Operation.
7-6 7.5 Maintenance (Deleted Except for 7.5.7) 7-8 7.6 Operational Testing of Nuclear Safeguard Systems 7-8 7.7 Deleted.
8.0 Research and Development Program.
8-1 8.1 Developmental Puel Design Features B-1 8.1.1 Zr-Cr Alloy Test Bundle.
B-1 8.1.2 Thin Clad Power Tael Bundle.
8-5 8.2 Principle Devel( caental Fuel Operating Limitations 8-5 8.2.1 Center Melt Test Puel Bundles.
8-5 90 Primary System Surveillance 9-1 10.0 (Section 6.0) Administrative Controls 10-1 6.1 Responsibility 10-1 6.2 Organization 10-1 6.2.1 Off Site 10-1 6.2.2 Plant Staff..
10-1 6.3 Plant Staff Qualifications 10-1 6.4 Training 10-5 6.5 Review and Audit 10-5 iii
_ =. -
t,.
B.
Remove Page 10-2, " Figure 6.2.1, Consumers Power Company Off-Site I
i Organization," an5 replace it with the following:
i i
I i
4 a
4 1
0 i
l
~
l 1
1 i
1 I
I J
I j
l i
4 8
5 4
I 4
{.
~
/
i
+
2 a
4m 4
Y
.m-,
Consumers Power Company OFF-SITE ORGANIZATION PRESIDENT i
EXECUTIVE VICE PRESIDENT f,
SAFETY AND AUDIT VICE PRESIDENT REVIEW BULK POWER OPERATIONS BOARD I
I l
l l
1 1
MANAGER OF MANAGER OF DIRECTOR OTHERS MANAGER PRODUCTION-NUCLEAR MAINT &
.OUALITY OPERATING SERVICES ADM SERVICES ASSURANCE T
GENERAL SUPT QA C
ADM SERVICES ADMINISTRATOR pggg7 SUPERINTENDENTS Q
(NUCLEAR)
N NUCLEAR TRAINING ADMINISTRATOR Z
FIGURE 6.2-1 10-2
1 p
-(-
C.
Remove Page 10-3, " Figure 6.2-1 Consumers Power Company Big Rock Point Organisation," and replace it with the following:
i i
II r
i d
.l i
i f
i
(
t 3
.m.
--,_.m.
Consumers Power Company BIG ROCK POINT Organisotion OA-ADMIN OFF-5ITE PLANT SUPERINTENDENT 1
PLANT REVIEW COMMITTEE OA SUPT CLERKS PERSONNEL T ECHNICAL DIRECTOR ENGINEER OPERATIONS SUPERINTENDENT ADMINISTRATIVE SOL (o)
SUPERVtSOR HEALTH PHYSICIST TECHNICAL SUPERINTENDENT MAINTENANCE SUPERINTENDENT I
I SECURITY CHEM & RAD PROT SUPV l ENGINEER l SUPERVISOR d i AC SUPERVISOR l TRAINING S S l REACTOR ENGINEER l
CHEM & RAD PROT l
ENGINEER PLANT TECHMCIANS TECHNICIANS I
OPERATIONS SUPERVISOR l ENGINEER l SOL (b)
MAINTENANCE SUPERVISOR PLANT SHIFT SUPERVISORS ASST MAINTENANCE SUPERVISOR l
l l
"O OPERATORS REPAIRMEN JL - Senior Operator Licensee a)The Operatier+ Superintendent etied not hold an SCL provided be meets the othar requirements of 6 31 of these specifications and the position of "Op-rations h erviser" is filled. t!nder these conditions, the Operations Supervisor shall be rec.onsible for directir4 the activities of licensed i
operators.
b)This position need not be filled if the Operations Superintendent holds an SCL.
riGuRE 6. -i 10-3 g
N r--
L D.
Remove Pages 10-7,10-8,10-10 and 10-11 and replace them with the following:
P O
u
6.5 1 ( Cont'd) 6.5 1.T AurHORITY The PRC shall:
a.
Reconmend to the Plant Superintendent written approval or disapproval of items considered under 6.5 1.6(a) through (d) above.
b.
Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
c.
Provide immediate written notification to the Manager of Production, Nuclear and y
the Cnairman of SARB of disagreement between the PFC and the Plant Superintendent.
However, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above.
6.5.1.8 RECORDS The PRC shall maintain written minutes of each meeting and copies shall be provided to the Manager of Production, Nuclear, the Chaiman of SARB, PRC members and alternates.
6.5.2 SAFETY AND AUDIT REVIEW BOARD (SARB) 6,5.2.1 RESPONSIBILITIES SARB is responsible for maintaining a continuing examination of designated plant activities.
In all cases, where a matter is formally considered by SARB, its findings and recommendations are communicated in writing to the Vice President - Bulk Power Operations (MO) and other appropriate levels of management. A written charter is prepared and approved by the Vice President - BPO which designates the membership, authority and rules '
conducting the meetings. Board membership, qualifications, meeting frequency, quorum, responsibilities, authority and records are in accordance with the nuclear plant Technical Specifications and ANSI N18.7-1972.
6Property "ANSI code" (as page type) with input value "ANSI N18.7-1972.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..;.2.2 FUNCTION The SARB shall function to provide independent review of designated activities affecting safety-related components, systems and structures designated on the plant's Safety-Related Quality List contained in the Consumers Power Company Quality Assurance Program.
10-7
6.5 2 (cont'd) 6.5 2.3 COMPOSITION AND QUALIFICATIONS Collectively, the personnel appointed for the SARB by the Vice President - BPO shall be competent to conduct reviews and technical audits in the following areas:
a.
Nuclear power plant operations.
b.
Nuclear engineering.
c.
Chemistry and radiochemistry.
d.
Metallurgy.
e.
Instrumentation and control.
f.
Radiological safety.
g.
Mechanical and electrical engineering.
h.
Quality Assurance practices.
An individual appointed to the SARB mt.y possess expertise in more than one of the above specialties. He should, in general, have had professional experience at or above the senior engineer level in his specialty.
6.5 2.h ALTERNATE MEMBERS Alternate members may be appointed by the Vice President - BPO to act in place of members during any legitimate and unavoidable absences including a conflict-of-interest determination.
The qualifications of alternate members shall be similar to those members for whom they will w
substitute.
6.5.2.5 COY ',TANTS Consultants shall be utilized as determined by the SARB members and/or chairman to provide expert advice to the SARE. SARB members are not restricted as to sources of technical input and may call for separate investigation from any competent source.
10-8
m 6.5 2 (Cont'd)
The status of deficiencies identified by the Quality Assurance Program, including the h.
effectiveness of the corrective actions completed and implemented, at least once every six (6) months.
- i. Audits of the Security Program required by the " Nuclear Power Plant Security Plan."
6.5 2 9 AUDITS Audits of safety-related facility activities during operations are performed by the Quality Assurance Department - BPO in accordance with the policies and procedures of the Consumers Power Company Quality Assurance Program. Quality assurance audit reports are sent to SARB for review.
In addition, technical audits are the responsibility of the Technical Services Department and shall be reviewed by SARB. These technical audits encompass e
The conformance of f acility operation to all provisions contained within the Technical a.
~
Specifications and applicable license conditions at least once per year.
b.
The performance, training and qualifications of the entire facility staff at least once per year.
The facility Site Emergency Plan and implementing procedures at least once per two years.
c.
Any other area of facility operation considered appropriate by SARB or the Vice President - BPO.
d.
6.5 2.10 AUI'HORITY SARB shall report to and advise the Vice President - BPO on those areas of responsibility specified in 6.5 2.8 and 6.5 2.9 6.5 2.11 RECORDS Records of SARB activities shall be prepared and distributed as indicated below:
Minutes of each SARB reeting shall be prepared and forwarded to the Vice President - BPO and a.
each SARB member within fourteen (1h) days following each meeting. Minutes shall be approved at or before the nert regularly scheduled meeting following distribution of the minutes.
If not included in SARB meeting minuten, reports of reviews encompassed by Section 6.5 2.8 b.
above shall be prepared and forwarded to the Vice President - BPO within fourteen (1k) days following corpletion of the review.
10-10
m k
6.5 2 (Cont'd) c.
Audit reports encompassed by 6.5.2.9 above, shall be forwarded to the Vice President -
BPO and ' cagement positions responsib3 e for the areas audited within thirty (30) days after completion of the audit.
t 6.6 REPORTABLE OCCURRENCE ACTION 6.6.1 The following actions shall be taken in the event of a reportable occurrence:
The Commission shall be immediately notified pursuant to 6.7 or a report submitted pursuant a.
to the requirements of 6.9 m
b.
All events which are required by regulation or Technical Specifications to be reported to the NRC in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shall be reviewed by the PRC. The results of the PRC review shall be submitted (either by PRC minutes or by separate report) to SARB and the Manager of Production, Nuclear.
6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The reactor shall be shut down immediately and not restarted until Comission authorization is received [10 CFR 5^.36(c)(~,(i)).
b.
The Safety Limit violation shall be reported immediately to the Commission in accordance with 10 CFR 50.36, the Manager of Production, Nuclear and to SARB Chairman or Vice-Chairman, c.
A report shall be prepared in accordance with 10 CFR 50.36 and 6.9 of this specification.
The Safety Limit violation and the report shall be reviewed by the PRC.
~
d.
The report shall be submitted within 10 days to the Commission (in accordance with the requirements of 10 CFR 50.36), SARB Chairman and the Manager of Production, Nuclear.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained for all structures, systems, components and safety actions defined in the Big Rock Point Quality List. These procedures shall meet o* exceed the requirements of ANSI-18.7 10-11 h
m
?
?
l i
E.
Remove Table 6.2-1, " Minimum Shift Crew Composition," and replace it with the following:
(
t 5
e
m TABLE 6.2-1 Minimum Shift Crew Composition The minimum shift crev shall be as-follows except when plant conditions specified in paragraph (a) or (b) below have been established (see note (1) below) or when an unexpected absence occurs (see note (2) below):
1 Shift Supervisor - SOL 1 Operator - OL l
2 Operaters - Nonlicensed
( e.) Cold Shutdown r,
1 Shift Supervisor - SOL 1 Operator - OL 1 Operator - Nonlicensed (b) Refueling Operations (See note (2) below) 1 Shift Supervisor - SOL 1 Operator - OL 2 Operators - Nonlicensed SOL - Senior Operator Licensed in accordance with 10 CFR 55 OL - Operator Licensed in accordance with 10 CFR 55 (1) During control rod motion associated with reactor start-up (to a power level > 5 percent), one licensed Operator shall observe the control rod manipulation to ensure established control rod withdrawal pro-cedures are adhered to.
(2) Does not include additional personnel required when core alterations are being conducted. See 6.2.2.e.
(.
II.
Discussion A.
Changes to the Index Page iii of the index utilized in the development of the Administrative Control Technical Specifications issued December 19, 1975 did not reflect previous changes made in Section 8 of the Technical Specifications. On December 18, 1970 Consumers Power Company requested a significant change in Section 8 of the Big Rock Point Technical Specifications. Technical Specifications Change No 22, approved by the NRC February 29, 1971, ap-proved significant changes in Section 8.
The change in the index pro-posed in this change merely updates the index to be consistent with the February 9,1971 Technical Specifications change.
B.
Management Organization At the time of the issuance of the December 19, 1975 Administrative Con-trol Technical Specifications, the Consumers Power Company organization contained a Vice President - Bulk Power Operations and an Executive Manager - Bulk Power Operations. On January 1, 1976 Mr R. A. Lamley retired from Consumers Power Company. Mr C. R. Bilby, formerly Executive Manager - Bulk Power Operations, was appointed to Vice President - Bulk Power Operations to replace Mr Lamley. At present, Consumers Power Com-pany does not plan to fill the slot vacated by Mr Bilby. Thus, Figure 6.2-1 and Pages 10-7, 10-8, 10-10 and 10-11 have been appropriately re-I vised to reflect this organization change.
C.
Big Rock Point Organization Change e
A position of 0perations Supervisor has been created in order to lighten the workload on the Operations Superintendent. This position is reflected on the Big Rock Point Organization Chart included in this proposed change.
In addition, provision has been made such that a licensed Senio: Reactor Operator is required to directly supervise the shift supervisors.
1 D.
Change in PRC Authority A typographical error apparently occurred in Section 6.5.1.7(b) on Page 10-7 The Standard Technical Specifications and the Palisades Plant Technical Specifications require PRC to render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question.
The Technical Specifications issued for the Big Rock Point Plant Decem-ber 19, 1975 contained a similar requirement except that "e" was re-placed with "f."
We believe this was a typographical error and request that it be changed to "e."
E.
Minimum Operating Crew Complement g
The new Administrative Control Technical Specifications require that one Benior Licensed Operator, two Licensed Operators and/tvo Nonlicensed 6
l
f.
r
(
III. Conclusions Based on the foregoing, both the Big Rock Point Plant Review Committee and the Safety and Audit Review Board have concluded that this proposed Tech-nical Specifications Change does not involve an unreviewed safety question.
CONSUMERS POWER COMPANY 1
f.
I By C. R. Bilby, Vice Presi Sworn and subscribed to before me this 8th day of March 1976.
JAu AAR Sylvia B( Ball, Notary Public Jackson County, Michigan My.comtission expires May 18, 1976.
N I
(
8 f
4
u.3. NUCLE AR CEGULATORY CoMM:P C"N DOCKE7NUMIEG NRCFOoM 1S5 50-155 2
uae
.N7C DISTRIBUTION roR PART 50 DOCKET MATERI AL
^
TL:
NRC FROM:
Consumers Power Co.
DATE OF DoCUM".NT 3-8-76 Jackson, Michigan 49201 Ralph B. Sewell DATE RECElVED M TTER
@ N OTORIZ E D PROP INPUT FORM NUMBER OF COPIES RECEIVED fl:ERIGIN AL
@VNC LASSIFIE D kb OCoPY DESCRIPTION Ltr tranS the followiry :
E NCLOSU RE Request for Change to the Tech Spces for Lic. DPR-6 notarized. $-8.-76 to reflee changes in General Of fice {x plant '4taf f organi:
tion 1& to propose minof changes &,2 corrections to Tech S1 pes.....
(3 Orig & 37 CC rec'd) 7,.
9, j cr e P'C.M k.;s.uw 4.
[ ;i [ (~ " '
"r 2 "-
PLAh7 NAME: RaituaduxxRiant Big Rock Pt. Plan :
SAFETY FOR ACTION /INFORMATION ENVIRO un t, 3-1J-/6 i
~
ASSIGNED AD :
,,l ASSIGNED AD :
]
BRANCH CHIEF :
(
Qantn MM BRANCil CllIEF :
l V
PROJECT MANAGER:
g yg3 PROJECT MANAGER :
I
]
LICTA'S$T. :
R. 01 gs5 LIC. ASST. ;
INTERNAL OlSTRIBUT'ON
,M. REG FIIf D SYSIEMS_SAEETY PTANT CYSTEMs 1:NV.IRn peu NRC]DR HEINEMAN TEDEScn ERNST r
V I&_E_h SCHROEDER BENAROYA BALIARD
. _V __0 ELD LAINAS SPANGLER
_ V GOSSICK & STAFF ERGINEEglNG IPPOLITO
_ ___ l S1TE TECH
___MIPC MACCARy CASE KNIGHT OPERATING REACTORS GAQllLL 114NAltER SIIMEIL STELI.a STEPP 11ARLESS PAULICKI IlUIE\\N OPERATING TECH l
PROJECT !!ANAGEMENT REACTOR SAFETY
/I EISENHUT j_ SITE ANALYSIS BOYD ROSS t/' SilA0 VOLIJER P. COLLINS NOVAK
/
BAER BUNCH
~
IIOUSTON ROS7.TOCZY
/
SCIUENCER F
J. COLLINS PETERSON CHECK F
GRIMES KREGER MEffZ
~
llELTEMES AT & I SITE SAFETY & ENVIRf SKOVIIOLT SALTZMAN ANALYSIS nr g g
. "k I " i I O kl I I--
RttrBERG DENTON & MULLER P I E
n I
9[II1 EJ 4I 3 *
- " tOf8E A"t3.#tW EXTERNAL 0lSTRIBUTION
~ g LPpa: Charlevoix, Mi ch NATL; LAB l
liRDdkiiF/EN NATL LAB ~
. /
_ IJ SIC IA _P_DR h
/
ASLB CONSULTANTS F
..-_hCRS Ib m !Sg t_TO A
- A*
N=cFoxu.,,.,..